JPRS ID: 9725 USSR REPORT ELECTRONICS AND ELECTRICAL ENGINEERING

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• Content Type: REPORTS

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_ JPRS Ll9725
11 Nlay ~~1~~81
~
' USSR Re ort ~
p
ELECTRONICS AND ELECTRICAL ENGINE~RING
CFOUO 5/81 ~
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JPRS L/9725
11 May 1981
USSR REPORT
ELECTRONICS AND ELECTRICAL ENGINEERING
(FOUO S/81)
C9NTENTS
CERTAIN ASPECTS OF PHOTOGRAPIiY, t40TI0N PICTUItES AND TELEVISION
Vidicon Target 1
ELECTRICAL ENGINEERING EQUIP2~NT AND MACHINERY: APPLICATIONS AND TfIEORY
Studies of the Overload Capacity of High-Voltage Breakers......... 2
ELECTRON AND ION DEVICES; EMISSION; GAS-DISCHARGE AND ELECTROI~-BEAM
- DEVICES
~
General-Purpose Source of Negative Ions With Cathode Sputtering... 7
Stabilization of the Operating Mode of the Ion Source for an
EG-2.5 Electrostatic Accelerator 8
Ion Injector for an Electrostatic Accelerator 8
Source of i4ultiple-Charge Ions of Gases for Electrostatic
_ Accelerators 9
Instrument for Measuring the Emittance of Charged Particle Beams.. 9
Linear Ion Accelerator............ 10
- Accelerating Tube for an EG-1 Electrostatic Accelerator........... 11
Pulse Operation of the EG-1 Electrostatic Accelerator at the
Physico-r^.nergetics Institute 11
Device for Forming a Pulsed Electron Beam 12
Optimization of Quasi-Periodic Structures in a Linear Resonance-
Type Ion Accelerator 13
- a- [III - USSR - 21.E S&T FOUO]
~
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System for Stabilizing and Measuring the Energy of an Ion Beam
in an Electrostatic Accelerator With Ov~-charge of Ions......... 13
EGP-15 Overcharge-Type Electrostatic Accelerator (Design ~
Project) 14
Experience With High-Voltage Accelerators in Service at the
Physico-Energetics Institute 15 =
Design of the Ion Optics for the ESU-2.5 Electrostatic Accelerator
at the Kharkov State University 15
Magnet System ~6
- Mezhod of Accelerating Positively Charged Particles 17
Method of Accelerating Ions 17
- Small-Size Accelerator of Heavy Ions With a 1 MeV Energy of
Yarticles 18
- Interference of Synchrotron Radiation 18
Screen for a Cathode-Ray Memory Tube 19
ENERGY SOURCES
Some Electrotechnical Problams af Controlled Thermonulcear
Fusion........~ 20
- Electromagnetic Systems of Tdka.ma'.cs 31
Power Supply System for the Tokamak Type Thermonuclear DE:vices.... 50
Powerfut r~C Units With Inertial Energy Storage Elements for
Feeding Electrophysical Devices 59
Prospects far the Application of Shock Homopolar Generators for
- Supplying Power to Thermonuclear Devices 66
- Disc Type Shock Homopolar Generator With Gas Rotor Bearing........ 73
Gas Bearings of the Rotors of High-Speecl Unipolar Machines........ 80
Capacitive Storage Elements as a SoLrce of Power fox Controlled
Thermonuclear Fusion 88
Thyristor Feed Systems for Experimental Thermonuc.lear Reactors.... 104
- b -
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_ Creating the Electric Feed ~ystem~ of In~ectors for
Thermonuclear Devices 110
Design of Power Systems for the In~ector Complexes of
- Thermonucl.ear Reactors 12~
a Electric Power Supplies for the In3ection Systems of
- Thermonuclear Devices 126
Some Aspects of Controlling Tokamaks 135
Tokamak Plasma Column Position Control System 140
INSTRiTrfENTS, MEASURING DEVICES AND TESTERS, METHODS OF MEASURING,
- GENERAL EXPERIMENTAL TECHNIQUES
_ A Device for Testing Integrated Circuits 154
~ OPTOELECTRONICS, QUASI-OPTICAL DEVICES
. System of Scanistor Characteristics and Parameters 155
Noise in the Microzone of a Semiconductor Scanistor 156
~ Areas of Application for Continu~us and Multielement Types of
Two-Coordinate Scanning Semiconductor Photodetectors and a
Comparison of Their Characteristics 156
Performance of an MF-16 Photomatrix in the Signal Detection
Mode 157
- An Output Screen for a Brightness Intpnsifier 158
A Device for Controlling the Image Brightness of an
Electrooptical Transducer ~58
A Multichannel Electrooptical System 159
- A Multicavity Image Brightness Int~nsifier 159
PUBLICATIONS
Ad~ustment of Telemechanical Devices at Industrial Enterprises.... 1b0
Ad~ustaUle Self-Compensatiz~g Electrical Power Transmissipn Lines.. 162
Autonomous Multiphase Voltage Inverters With Improved
Characteristics 164
_ Contact Interference in Radio Reception 167
- - c -
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Divergent Electrical Prospecting 169
Elements of Optoelectronic Devic~s 171 .
Evaluation of the Effectiveness of Complicated Technical Devices.. 172
- Fundamen.ta]s of the Physics of Semiconductor Layered Systems...... 175
Handbook of Measuring Instruments for Radio Components............ 177
New Book Discusses Statistical Radiometry 182
Radioelectronics and Communications~in the National Economy....... 185
Sys~ems of Space and Time Conversion of Information. 189
Technical and P;conomic Effectiveness of Complex Rad ioelectronic
Syatems 192
Theory and Circuits of Increased Frequency ~hyristo r Inverters
With Width Regulation of Voltage 197
- Transient Electromagnetic Processes in Systems With Rectifiers.... 200
SEMICONDUCTORS AND DIELECTRICS, CRYSTALS IN GENERAL
Effect of an Electric Field on Recombinat3on Proce s ses in
- CdS:Cu Single Crystals 203
A Method of Measuring the Effective Mass of Current Carriers
in Semiconductors at Microwave Frequencies 204
Unbalanced Luminous Rectification of Bands in Scho t tky Barriers
Based on Wide-Band Semiconductors 204
- d -
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a
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CERTAIN ASPECTS OF PHOTOGRAPHY,
- MOTION PICTURES AND TELEVISIO~I
UDC 621.385.832.564.4(088.8)(47)
VIDICON TARGET _
~ USSR Patent Class H O1 J 29/36, No 2,543,928 17 Mar 80 (disclosure No 721,865
15 Nov 77)
MATVEYEV, V. G. and TAZENKOV, B. A.
[From REFERATIVNYY ZHURNAL: EI,EKTRONI1tA in Russian No 1, Jan 81
Abstract No 1A110 P]
[Text] The vidicon target consists of a translucent dielectric substrate with ~
, a photoconducting layer. In order to increa~e the signal multiplicity and the
sensitivity while reducing tl~e inertia, a reticular electrod~ is deposited on
the substrate on the side of the photioconducting layer and this la~er contains
a mosaic of conducting electLodes which pass across it, each aligned with the
center of a ce11 of the reticular electrode.
COPYRIGHT: VINITI, 1981 -
[177-2415]
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ELECTRICAL ENGINEERING EQUIPr1ENT AND
- MACFiINERY: APPLICA~IONS AND THEORY ,
~
UDC 621,316.54.001.4
STUDILS OF THE OVERLOAD CAPACITY OF HIGH-VOLTAGE BREAKERS
Moscow ELEKTROTEKHNIKA in Ru~sian No 1, Jan 81 pp 56-57
(Artic;ie by V. I. Shutskiy, doctor of technical sciences, prof essor, V. B. Narozhnyy,
candidate of technical sciences, Yu. Ao Fominykh, engineer]
[TextJ Gne way of ~.mproving the efficiency of the application of high voltage elec-
trotechnical equipment and, above all, commutation equipmsnt (breakera and discon-
nects) is use of their overloau capacities. When designing the high-voltage
~ breakers, disconnects or other high voltage equipment certain relations cannot be
determined in advance which are especially important for operat ion. For exa.mple,
these are the admissible ~oad currents as a function of the ambient temperature or
the time of their oper,ation. These values usually are found experimentally when
testing the already built units.
The relations constructed on the basis of the experimental dat a have, as a rule,
the following basic deficiencies: a) in all cases the coordinates of the points are
dietorted as a'result of unavoidable experimental errors, and they must be "smooth,"
that is, averaged; b) the values of a number of intermediate points are unknown;
c) it can become necessary to extrapolate the relation obtained, that is, f ind
- values of the points lying outside the experimental range. It is possible to avoid
such deficiencies if a functional relation between the investigated parameters is
found by the experimental data. The problem reduces tc determining the relation
- which corresponds to the true relation with a suff icient degreE of accuracy.
In electrotechni.cal calculations, just as in other fields of engineering, for pro-
~ cessing experimental data the most widespread accuracy criterion of the approxima-
ting function is the least squares criterion [1]. Let us cons ider the prolonged
admissible load current cf an oil-f illed VNIB-10-630-10 breaker as a function of its
operating time. This relation can be described by thQ express ion [1]
- ~l)
1~ =utbe~t -4- ~xow~
(1~ ~2~
Key: 1. long 2. rated
where t is the operating time of the load current, minutes; Ir ated is the rated cur-
rent of the investigated breaker, amps; a, b, c are the desir ed coefiicients of the
curve equation.
2
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The coefficients a, b, c are defined by the known transformations, as a result of -
which we obtain the system of equations:
' n n n
zF b~ D~ c~ t t=~j yt: _
t=t r_~ t_i
n n n . n ~2~
F~j Dt~-h ~ D'~-Fc~ t~Dt=~j ytDt~
t_i r-~ t-t t_f
n R n n
F~j t~'~'b~j riDi'~'~~ ~st =~j ylti�
1=1 i_I i-1 1=1 ) -
In the system of eq~iations (2) the following notation is used:
yr-?.ln (/t-/so~) ~ F-rln a; Dr--?ln !r,
_ (a1 .
Key: a. rated
- where n is the n~ber of ineasurements t~'icen; i is the order numbe.r. of the measure-
ment. ~
For the solution of such systems, that is linear algebraic equations up to third
. order on a computer usually the Kramer method is used ~2]. In the given case this
method cannot be used inasmuch as, as the calculations have demonstrated, the value
of the determinant of the system turns o~it to be c~ose to zero, which does not _
permit us to obtain a stable solution. _
From expression (2) it is obvious that the matrix of the system is symmetric. The
most exact solutions, as the analysis demonstrated, is provided in this case by the
method of one-way rotations [3]. For dascription of the realized algorithm for the
solution of system (2), let us introduce the following nc~tation: A-- the qua.dra-
tic matrix (system matrix); B-- the vector of the free terms; X-- vector of un-
knowns.
Then Att ~ Akt'� `
Mk` YA'rt A'kt ' ~k` - - �4'u A'~r ~ ~3~ _
- where i= l, 2, n- 1; k= i+ 1, i+ 2, n. For Aii Aki = 0 we have
Mlci~l, Lki=O.
- Then the system is transformed by the formulas:
Mk19i Lkidlk = MktBI '_RLRJBk~ l
Lu~t - MkrBt = Lk~B~ - Mkr~x~ J ~4~ -
where yi, yk are the left-hand sides of equations i and k, respectively; Bi, Bk are _
the right-hand sides cf eq~iations i and k, respectively.
_ After n(n - 1)/2 steps we arrive at the system
A~, ~X - 8~,~, ~ 5 )
3 _
.
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rj - i
I ~(~.il-,v; z~=E(l,M.~Tl~,I)c ~l~..~I=~(?,".Tl~ fIt ~
~ ~lz.~1=~l41I; ~lT.z1=E(~~M~~l~~I~Zk A~7.3I=E(1,N,7~l,rlxi~~li,i11: I
I A(A~�A[f,d~~ A~J,TJ=A[~1,3I~ ~~JJI=~(~~N,~[l,IJIT)~ I
e1~1�~~/ N, i~ r12.~1~ sl~r(i H, lnT[f.t1. i~ r(z,~1; I
. I e[a)=af~ N, rli,tl.~~ r[r..(1
_ L_ ,
r-I_, ,
I f� I
I !
I N=A[I,lJ~ ~A !,!)11~A(N,II ~Z)~ ' ~Nf-1 l-~~ I
L=-A(k,l)~M
~ k.~I=o ~=a ~
. I f-f+~ k=� ~ '
a-~; c=o ~ I
~ I -
I ,r~yxA[!�I~-LXA(K.1I~ ~~I~II=R I
_ I A~K~II=LxA(l,./J;M"~~K I
~ I
i f f+l 'cN1 k~Mf I - -
I . . . I -
I R=N"6~I LxD[KI; M=p~s[Nl-KJxA[l,Nl-K) I
B[KJ=LxE~~I~MxB~K~~ I
~ e~:R '~-k+1 I
I R-~Ya/ M~A'1-I-1 ~ -
~ I `
= I l~l 1=1-1 s~!)=(d(jI'MI~~CI fI i -
' ~
r~ -
~+=exp(sldl ~ B=s~t); s=sl31 ~
I---------------
Block diagram of the program for calculating the admissible
load current of high-voltage breakers as a function of the
time of its effect.
Table 1. Experimental an~ calculated values of the overload cu*-rent as a function _
af the ti.me of its e.ffect (VMB-10-630-10 breaker)
Time the overload current flows, sec
Parameter -
8 g-) 120 110 I 2~0 I 420 I 720 I 3000 5100 I 28 AOD c>
: I
_ Experimental values of ~ -
overlc;ad current, amps ~a ~ 800� I ~0� +70~' ~ +2'0 ~ ~sso 3��� z��� i5�� ~0
alues of i ~ ~ ~ { 2 ~
Calculated v 1
overload current, amps ~o+~ 78~ 5700 ~+90� I 3~0o a~oo I s~oo I isso I i~oo t- I~_
t4.0 +7.7 I -4.5 I-10,5 -9,4 -9,5 =10,5 ~ -?1,0 -2.5 0 I
Error, %
4
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Table 2. Experimental and calculated values of the overload current as a function
of the time of its effect (I~IICP-35-1000-25 and VMO-27.5-1000-25 breakers)
'Time the overload current flows, sec
~ Parameters --rt----
~ 6 10 25 30 40 50 270 600 1800 3600 f8 000 32 400 ao
Experimeni.al
values of the
overload cur-
rent, amps ~s o00 20 000 !~s o00 ~o 000 900o eooo ~ooo ao~o ~ooo aooo ssoo . ~oo0 150~ ~ ioo
~
Calculated
values of the I
overload cur-
rent, SII1F$ 19~.2j I .F.1 6 ~~}18 ~-4 0 --~a,8 ~11 -874~ ~+2.8G~ f3835 I +3,~17 -I-1432 t1260 -d~7 0 -
Error, % ' -
System (5 j is solved by the usual inverse method, that is,
Xm=~Bm(~r--Amt~f~m+~-..._AAmn(l~n~Ammft)r ~V~
where m= n, n- l, l.
The block diagram of the calculation pr~gram is presented in the figure. The pro-
gram is written in ALGOL-60 and is executed on tt~.e BESM-4m computer.
- The program consists of three m~dules,; 1-- shaping the matrix of the system and
- the vector of free terms; 2-- execution of the algorithm; 3~~ determination of ~
. the unknown coefficients of the equation.
In Tables 1 and 2 the experimental and computer-calculated adml.ssible values of the
load currents are presented as a ~unction of the time of their effect. As is ob-
vious from the tables, the values of the load current (that is, the overload) ob-
- tained experimentally and calculated by the proposed procedure ior certain investi-
- gated types of breakers, in particular, for the VMB-10-630-10, MKP-35-1000-25 and
VMO-27.5-�1000-25, compare satisfactorily.
It is necessary to note that in practice the approximation can be quite accurate
when the statisi.ical data are not distorted by random errors. In the Fresence of
the latter (the person conducting the experiment should not be fr.3ghtened by tliem),
usually a"smoothing" approximation by functions tha t minimize either the mean square
error or the absolute error in the entire experimental range is used. This method _
is also applied by the authors. From Tables 1 and 2 it is obvious that in indj.vi-
dual intervals the divergence of the calculated and the experimental data can be
significant (to 21%), but the mean square errors in the calculated data in the -
entire experimental period do not exceed 5%, This error is entir~ely admissible for
calculating the overload capacity of the high-voltzge breakers and also other
- electrotechnical equipment with the help of a computer.
5
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_ ~
BIBLIOGRAI YiY ~
1. Yu. A. Fominykh, V. B. Narozhnyy, "Calculating the Overload ~apacity of High-
Voltage Breakers," ELEKTRICHESTilO (Electricity), No 7, 1974.
2. I. S. Berezin, N. P. Zhidkov, METODY VYCHISLENIY (Calculation Techniques), Vol ~
II, Moscow, Fizmatgiz, 1560, '
3. V. N. Kublanovskaya, "Some Algorithms for Solving the Complete Problem of Eigen- ;
values," ZHURNAL VYCHISLITEL'NOY MATEMATIKI I MATEMATICHESKOY FzZIKz (J.ournal ,
of Computational 1~Iathema.tics and Mathematical Physics) , Vol 1. No 4, 1961.
CORYRIGHT: Energoizdat, "Elektrotekhnika", 1981 ~ -
[161-10~45]
~ 10845
CSO: 1860
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ELECTRON AND ION DE4iCES; EMISSION;
~ GA~-DISCHARGE AND ELECTRON-BEAM DEVICES
- UDC 621.384.6
- GENERA'L-PURPOSE SOURCE OF NEGATIVE IONS WIT~;. CATHODE SPUTTERING
J Khar' kov VOPROSY ATO:~IIdOY NAUKI T TEKZiNIKI : OBSHCHAYA I YADE1tNAYA FIZIKA in
~ Russian No i/12 1980 pp 56-5$
KOZLOV, V. G., OVSIYENKO, G. P. and CHEKANOV, S. Ya.
[From REFERATIVNXY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 Abstract No 1A173] -
_ [Text] The construction of a ge~eral-purpose source of negative ions with cathode
sputtering is described. The conditions under which a t;z~ of primary negative
ions forms are ~xamined. Also established is how the ~iield of secondary negative
, ions depends on the energy of primary Cs+ ions. It is shown that the y:teld of _
secondary neg~tive ions reaches the Sy maximum at an energy of Cs+ ions equal to
$ keV. The composition of a beam of negat i-ae ions has been analyzed mass-spec-
trometrically. Wi*_h a copper cathode, the Cu ions constitute 50% of the total
beam current.
COPYRIGHT: VINITI, 1981
- [177-2415]
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UDC 621.384,6
STABILIZATION OF THE OPERATING MODE OF THE ION SOURCE FOR AN EG-2.5 ELECTRQSTATIC
- ACCELERATOR
Khar'kov VOPROSY ATOMNOY NAUKI I TFKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA
in Russian No 2/12, 1980 pp 71-73
NIKITIN, V. A. and Y'AKUSHEV, V. P.
~
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
:b~tract No 1A174]
[Text] A system has been developed which stabilizes the operating mode of the ion
source for an electrostatic acce.lerator, the first stage of stabilizing the ion
current to the target. The current of the beam leaving the source is equal to the
difference between the current in the anode circuit and the cathode current. The
current in the anode ciruuit is stabilized by varying the plate voltage of the
high-frequency oscillator and the cathode current is maintained at its minimum
level by means of an automatic pulling device. This ensures a constant beam
current :Erom the source, and, consequently, a more stable ion current to the
target. The current in the anode circuit can be regulated over the 15-110 micro-
ampere range and the current fluctuations do not exceed 0.5% over a period of
2 h. Figures 3; references 4.
~ COPY~IGHT: VINITI, 1981
- [177-2415]
- UDC 621.384.6
ION INJECTOR F0~< AN ELECTROSTATIC ACCELERATOR
Khar'kov VOPROSY ATOMNOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA in
Russian No 2/12 1980 pp 81-83
= NOVIKOV, M. T. and TSYGIKALO, A. A.
[From REFER.ATIVNYY ZHURNAL: ELEKTRI)NIKA in Russian No l, Jan 81 Abstract No 1A175]
[Text] Following an analysis of expressions which relate the parameters o� an
ion beam at the entrance to and at the exit from, respectively, of an electro-
static accelerator, the design of an ion in~ector for use with a nondischarging
accelerator is proposed. Its special features include a preaccelerator with
automatic beam focusing at the injector exit, followed by better conditions for
matching the operation of the ion source and the operation of the accelerator
without impairment of the automatic beam focusing in the accelerator. Such an
8
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' injector is an autonomous device. Within certain limits it facilitates regulation
of the 3on-optical power of the lenses at the entrances to the accelerator and the
preaccelerator during operation and at the same time maintains the conditions for
- better matching of the ion source with the accelerator. Figures 1; reference~ 5.
f CUPYRIGHT: VINITI, 1981
[177-2415] �
- UDC 621.384.6
~OURCE OF :MfTLTIPLE-CHARGE IONS OF' GASES FOR ELECTROSTA'rIC ACCELERATORS
Khar�lcov VOPROSI ATOMNOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA in
Russian No 2/12, 1980 pp 69-70
PISTRYAK, V. M., KUZ'MENKO, V. V. and LEVCHENKO, Yu. Z.
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 Abstract No 1A176]
[Text] The design and the results of bench cesting of a source of multiple-charge
ions of gases are described. It is a source with cold cathodes and a Penning
- discharge. Its outside dimensions are a 200 mm diameter and a 100 mm height; its
maximum power requirement is 150 W. With neon as the working gas, the following
cu~+ents were recorded behind the exit gap of the mass-analyzer: Ne+ 160 microamp,
Ne 11 microamp, Ne3+ 0.8 microamp, Ne4+ 0.05 microamp. Figures 3; references 3.
COPYRIGkT: VINITI, 1981
- [177-2415]
UDC 621.384.6
INSTRUMENT FOR MEASURING THE EMITTANCE OF CHARGED PARTICLE BEAMS
Khar'kov VOPROSY ATOMNOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIK~'~ in
Russian No 2/12, 1980 pp 74-77
KUZ'MENKO, V. V. , BOGD~AI.IN, V. G. and PISTRYAK, V. M.
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 Abstract No 1A178]
~Text] The operating principle of this instrument for measuring the phase charac-
teristics of particle beams is based on the "two gaps" method with mechanical
9 ~
_ FOR OFF:~'IAL U~E ONLY
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scanning of the gap diaphragms. Both diaphragms can be moved through a distance of
+10 mm relative to the system axis, the first diaphragm either continuously or
~ discretely in controllable steps and the second diaphragm continuously. The
transit base of tlie instrument is 330 mm long, the angle resolution is 0.3 mred,
and the average measuring time is 10 min. The instrument can operate in three
modes: measure the current density distribution over the beam cross section,
plot curves of the phase density distribution characterizing the current in the
beam, and map the phase pattern of the beam compr~nent with a current density above
a preset level. Figures 9; references 3.
COPYRIGHT: VINITI, 1981
[177-2415]
'JDC 621.384.6 '
_ LINEAR ION ACCELERATOR
- USSR Patent Class H 05 H 9/00, No z,628,375 15 riar 80 (disclosure No 720,833
13 Jun 78)
AUSLENDER, V. L., BARANOV, I. A., LAZAREV, V. N., PANFILOV, A. D., SMIRNOV, B. M.,
TROFIMENKO, S. M., SHILOV, V. P. and EYSMONT, V. P.
[From REFERATI~INYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A179 P]
[Text] This linear ion accelerator consists of a coaxial resonator with a drift
tube, a vacuum space and a high-frequency pulse generator. In order to facili-
tate acceleration of several ion beams with generally different charge-to-mass
ratios and also to reduce the losses with producing several accelerated ion beams,
on the inner tube of the coaxial resonator are mounted several drift tubes which
form with its outer tube the same number of accelerating gap pairs.
COPYRIGHT: VINITI, 1981
[177-2415] ~
10
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UDC 621.384.6
ACCELERATING TUBE FOR AN EG-1 ELECTROSTATIC ACCELERATOR
Khar'kov VOPROSY ATOMNOY NAUKI I TEK~INIKI: OBSHCHAYA I YADERNAYA FIZIKA in
Russian No 2/12, 1980 pp 1Q0-102 -
ROMANOV, V. A., IVANOV, V. V., KRUPNOV, Ye. P., DEBIN, V. K., DUDKIN, N. I. and _
VOL~;~IN, V. I.
[From REFERATIVNYY ZHURN~L: ELEKTRONIKA in Russian No l, Jan 81
Abstract No 1A180J ~
[Text] The construction of an accelerating tube for an EG-1 electrostatic
accelerator is described. Most attention in its design was paid to increasino
the electrical strength of the accelerating gaps and to the conduction in vacuum
as well as to a better shielding of the insulators from charged particles. After
vacuum and high-voltage aging of this accelerating tube, nonanalyzed beams of
hydrogen ions with a current up to 80 microampere were f ound to form satisfactorily
with an energy within the 1.8-5.0 MeV range. Figures 4; references 6.
_ COPYRIGHT: VINITI, 1981
[177-2415]
UDC 621.381?.6
PULSE OPERATION OF THE EG-1 ELECTROSTATIC ACCELERATOR AT THE PHYSICO-ENERGETICS
INSTITUTE
Khar'kov VOPROSY ATONINOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA
in Russian No 2/12, 1980 pp 84-88
_ BOKHOVKO, M. V., VOLODIN, V. I., GLOTOV, A. I., DUDKIN, N. I., KANAKI. V. I., .
- KONONOV, V. N., POLETAYEV, Ye. D. and ROMANOV, V. A. ~
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
- Abstract No 1A181J
[Text] For the Furpose of broadening the scope of phys ical experiments with the
_ EG-1 accelerator as well as increasing its reliability and making it more con-
venient to operate, the entire complex has been redesigned to include a better -
ion source and a new chopping system with klystron bunching. The service life
of the ion source has been extended beyond 1000 h by changing the cathode material
and more smoothly regulating the magnetic field in its plasma discharge space.
The beam is chopped by rectangular voltage pulses and bunch~d by a sinusoidal -
voltage of 15.6 MHz frequency. The accelerator produced on a physical target ions
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.
beams with the following parameters within the 1.8-3.5 MeV energy range: ior.
current pulses of 0.3-0.5 mA amplitude and 15-25 ns duration in the plain chopping
mode and of 1.5-2.5 mA amplitude and 2-2.5 ns duration in the chopping with
_ bunchi.ng mode. In the microsecond mode of operation, moreover, the pulse durati~n -
was 0.1-1 microsecond, the pulse repetition ratz was 1.5-30 kHz and the pulse -
~ current was 0.3-0.5 mA. Figures 6; references 8.
_ COPYRIGHT: VINITI, 1981
_ (i~~-z4is~ _
- UDC 621.384.6
' DEVICE FOR FORMING A PULSED ELECTRON BEAM
- USSR Patent Class H O1 J 29/00, No 2,055,638 15 Jun 80 (disclosure No 741,347
20 Aug 74)
MATORA, I. M. and SHVETS, V. A., Joint Institute of Nuclear Research
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No l, Jan 81
Abstract No 1A182 P] ' -
[Text] This device for forming a pulsed electron beam consists of a pulse-type
electron gun with a cathode and a grounded anode and a source of accelerating
voltage. For monochromatization of the electron beam, the anode is built in the
form of a unit consisting of two semicylinders ~oined on the cathode side through
an annular jumper with one ~nd bent back, the opposite base of one semicylinder
is grounded and the opposite base of the other cylinder is connected to an addi-
tional source of pulse currents, connections also being made to the synchronizer
and the source of accelerating voltage.
COPYRIGHT: VINITI, 1981 -
[177-2415]
1
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APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000400010021-3
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UDC 621.384.6
OPTIMIZATION OF QUASI-PERIODIC STRUCTURES IN A LINEAR RESONANCE-TYPE ION
ACCELERATOR
Moscow IZVESTIYA VYSSHIKH UCHEBNYKH ZAVEDENIY: FIZIKA in Russian Vol 23, No 6,
_ 1980 pp 81-85 =
' GARASHCHENKO, F. G., S OKOL~JV, L. A. and TSULAYA, A. V.
[From REFERA,TIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 -
Abstract No 1A183]
_ [Text] A linear ion accelerator for operation with a rectangular or trapezoidal
_ accelerating voltage b etween the tubes is considered, and a m~thod of optimizing
its parameters is prop osed which carefully takes into account the quasi-periodi- ~
- city of their spacing. Numerical caZculations have demonstrated that the method _
~ is efficient and requ~res a rather simple structure for implementation. The
algorithm is shown in detail. The range of input phases is estimated, the maxi-
mum range exceeding the earlier predicted limits by a few percent.
~ COPYRIGHT: VINITI, 19 81
[177-2415] -
UDC 621.384.6
SYSTEM FOR STABILIZING AND MEASURING THE ENERGY OF AN ION BEAM IN AN Ei.ECTROSTATIC
ACCELERATOR WITH OVERCHARGE OF IONS
Khar'kov VOPROSY ATONINOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA in
Russian No 2/12, 1980 pp 32-34
AD'YASEVICH, B. P., VOROTINKOV, P. Ye., LARIONOV, L. S., POLUNIN, Yu. P. and
PCHELIN, Yu. A. -
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A184J
� [Text] For stabilizing and measuring the energy of accelerated ions in an EGP-8
electrostatic accelerator one uses a beam of neutral atoms formed during over- _
charge of negative ions. The neutral atoms then become charged into ions and
their energy is measured with an electrostatic analyzer. Crystals of CsI(T1)
separated by a thin opaque barrier and connected through light conductors to two
photoelectron multipliers serve as the detector. This detector also serves as a
sensor of the beam pos ition, its output signal corrects the voltage at the high~-
potential electrode of the accelerator with the aid of a corona triode. The
13 -
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system was tested in measurements of (p,Y) resonances and (p,n) threshold reac-
~ tions. A voltage stability and a beam energy uniformity within 4'10'4 were
attained, the solid opaque target contributing most to the nonuniformity of beam
energy. F'igures 2; references 7.
COPYRIGHT: VINITI, 1981
[177-2415J
I
UDC 621.384.6
EGP-15 OVERCHARGE-TYPE ELECTROSTATIC ACCELERATOR (DESIGN PROJECT) ~
Khar'kov VOPROSY ATOMNOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA i.n -
Russian No 2/12, 1980 pp 28-31
ROMANOV, V. A., BASHI~IAKOV, V. S., BORNOVALOV, N. G. et al.
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A185]
[Text] For the purpose of broadening the scope of physical measurements at the
Physico-Energetics Institute, an overcharge-type electrostatic accelerator (EGP-15)
is being built there which represents a modern version of the well known EGP-10
developed at the Scientific-Research Institute of Electrophysical Apparatus imeni
D. V. Yefremov. Its basic design parameters are: range of proton energies
3-15 MeV, maximum current up to 10 micr~ampere, range of accelerated ion masses
1-60, energy stability within 0.01%. For optimum transfer of continuous and
pulsed particle beams through the perforated accelerator target, a high-voltage
injector (VTI-300) has been developed for this EGP-15 which can deliver a beam
- witli a maximum energy of 300 keV. For formation of ultrashort ion clusters,
twofold bunching along the in~ection path is available. The operating modes o.f
this EGP-15 accelerator will be monitored and controlled with the aid of the
"Elektronika-100I" computer which serves as the basis of the automatic control
s}~stem for the electrostatic accelerators at the Physlco-Energetics Institute.
Figures 1; references 14.
COPYRIGHT: VINITI, 1981
[177-2415]
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I
FOR OFFICIAL USE ONLY
UDC 621.384.6
EXPERIENCE WITH HIGH-VOLTAGE ACCELERATORS IN SERVICE AT THE PHYSICO-ENERGETICS
INSTITUTE
. Khar'kov VOPROSY ATOMNOY NAUKI I TEKHNIKI: OBSHCHAYA I YADERNAYA FIZIKA in
Russian No 2/12, 19$0 pp 3-7 -
- ROMANOV, A., BAS~IAKOV, V. S., VOLODINA, A. P. et al.
[From REFERATIVNYY ZHi~RNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A186] -
[Text] Five high-voltage accelerators: EG-2.5, EG-1, EGP-lOM, IZG-2.5 and KG-0.3
are in operation at the Physico-Energetics Institute. These accelerators are
essentially intended for nuclear research. While they are in service, efforts
are constantly underway to improve them. In recent years most attention has been
paid to a changeover to their oper.ation with automatic control and to development
of accelerator tubes with a higher electrical strength, also to further improve-
ment of the pulse modes in accelerators EG-1 and EGP-lOP4. Performance parameters
- of these accelerators are given here, based on their operation in 19?8. Tables 6;
references 1.
COPYRIGHT: VINITI, 1981
[177-2415J
.
- UDC 621.384.6
DESIGN OF THE ION OPTICS FOR THE ESU-2.5 ELECTROSTATIC ACCELERATOR AT THE KHARKOV
STATE UNIVERSITY
Khar'kov VOPROSY ATOMNOY NAUKI I TEKHNIKI: OBSHCHAXA 1 YADERNAYA FIZIKA in
Russian No 2/12, 1980 pp 51-54
MASHICEIROV, Yu. G.
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A187]
_ [Text] The optimum conditions for acceleration of an ion beam in an existing
electrostatic accelerator are examined. The characteristics of the ion focusing
lenses and the parameters of the ion bean: are calculated on the basis of the
parameters of the actual accelerating tube, ion conductor and .r.otating magnet.
Al1 quantitites are regarded as strictly definite, except the parameter which -
characterizes the beam convergence at the entrance to the accelerating tube.
This convergence parameter is varied till the beam leaves the accelerating tube -
15
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I
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- as a conver.gent one and the beam crossover point becomes equidistant from the
end of the accelerating tube ar.d the lens which focuses thP beam on the entrance
gap of the rotat3ng magnet, this lens also being equidistant from that gap and
th~t crossover point. Better locations are found for the doublet of quadrupole
lenses which focus the beam on th~� ent:.ance gap of the magnet and for the lens ~
which focuses it on the target. Figures 1; tables 2; references 5. '
COPYRIGHT: VINITI, 1981 _
(177-2415]
UDC 621.384.6
MAGNET SYSTEM
USSR Patent Class H OS H 7/04, No 2,534,145 5 Jun 80 (disclosure No 736,388
17 Oct 77)
VASIL'YEV, V. V., MILYUTIN, G. V. and FURMAN, E. G., Department of Nuclear Physics,
Electronics and Automation at the Tomsk Polytechnic Institute
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No l, Jan 81
Abstract No 1A189 P]
[Text] This magnet system for an induction-typ e accelerator of charged particles
consists of a solid magnetic structure, an excitation coil connected to a pulse
voltage supply and a bias-magnetizing coil connected through an inductance to a
source of direct current. For reducing the distortion of the magnetic field pro-
duced by this electromagnet, an additional sour ce of direct current with a
shunting controlled rectifier is connected through a capacitance to the biasing
coil.
COPYRIGHT: VINITI, 1981
[177-2415]
,
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UDC 621.384.6
METHOD OF ACCELERATING POSITIVELY CHARGED PARTICLES
- USSR Patent Class H OS H 9/00, No 1,755,855 25 Mar 80 (disclosure No 422,128
6 Mar 72) ~
- LAVRENT'YEV, 0. A. '
[From RFFERATIVNYY ZHURNAL: ELEKT.RONIKA in Russian No 1, Jan 81
Abstract No 1A192 P] -
[Text) The method of accelerating positively chaxged particles differs from that
described in disclosure No 286,808 in that, for a more efficient accelerati~n,
the electr~n beam is made to radially converge toward the axis oc acceleration
of positively charged particles.
COPYRIGHT: VINITI, 1981
[177-2415] -
UDC 621.384.6
METHOD OF ACCELERATING IONS
USSR Patent Class H 05 I 9/00, No 1,756,267 25 Mar 80 (disclosure No 467,707
. 7 Mar 72) -
LAVRENT'YEV, 0. A.
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No l, Jan 81
Abstract No 1A195 PJ
[Text] In the proposed method of accelerating ions the lat~er are guided through
a sequence of potential wells formed by the space charge of electron fluxes which
have Ueen focused on the acceleration axis and have their density or energy modu-
lated in time as well as along the acceleration axis. For a more efficient accel-
eration, the electrons are in~ected from a cylindrical surface and retained within
the focus region by electric fields encompassing the acceleration axis.
- COPYRIGHT: VINITI, 1981
_ [177-2415]
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' ~rOR OFFICIAL USE ONLY
UDC 621.384.6:53
SMALL-SIZE ACCELERATOR OF HEAVY IONS WITH A 1 rieV ENERGY OF PARTICL~S
Khar'kov VOPROSY ATOMNOY NAUKI I TE:tHNIKI: OBSHCHAYA I YADERNAYA ~I2IKA in
Russian No 2/12, 1980 pp 94-95
- BEZUGLYY, V. V., BREDIKIiIN, M. Yu., IL'YENKO, B. P., NEKLYUDOV, I. M. and _
KHORENKO, V. K.
[From RE~'ERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 -
- Abstract No 1A197]
[Text] A sma11 co~apact accelerator of heavy ions has been developed for research ~
in field simulati.on of reactor defects, and its con~truction is described here.
Its main components are an accelerating tube at a 200 kV potential, a source of
multiple-charge ions, a beam forming system at the entrance to the accelerating
tube, and a target chamber. Use of a modernized source of multiple-charge ions _
makes it possible to produce, with a 200 kV potential at the accelerating tube,
beams of chromium, nickel, copper or other ions with a 1 MeV energy and a 20 uA
Current of accelerated particles. Experimental bombardment of targets with ions
of various elements has demonstrated that this accelerator can be successfully -
used for research in the physics of radiation damages. Figures 2.
COPYRIGHT: VINITI, 1981
[177-2415] .
UDC 621.384.6
INTERFERENCE OF SYNCHROTRON RADIATION
- Moscow ZIiURNAL EKSPERIMENTAL'NOY I TEORETICHESKOY FIZIKI in Russian Vol 79, No 3,
1980 pp 763-774
NII:ITIN, M. M., MEDVEDEV, A. F., MOISEYEV, M. B. and EPP, V. Ya.
[~'rom REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81 -
Abstract No 1A201]
[TextJ The phenomenon of interference of synchrotron radiation from relativistic
electrons is studied, this radiation being in synchronism with the particle beam
itself, successively at two points separated by a long straight gap. The spec-
tral characteristic and the polarization-angle characteristic of this radiation
- are analyzed. A satisfactory agreement is found between experiment and theory.
It is demonstrated that this interference of synchrotron radiation in units
where the magnetic field intensity drops sharply at the edge leading to a straight
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gap can be useful, independently or together w~th synchrotron and undulatory _
radiation, for solving a wide range of scientific and practical problems.
C01'YYtIGHT: VINITI, 1981 _
[177-2415]
UDC 621.385.832.82(088.8)(47)
SCREEN FOR A CATHODE-RA~ MEMOF.Y TUBE -
USSR Patent Class H O1 J 29/1~, No 2,586,392 15 Jul 80 (disclosure No 748,574
1 I~.ar 78) -
- PESKOVSKIY, V. T. _
[From REFERATIVNYY ZHURNAL: ELEKTRONIKA in Russian No 1, Jan 81
Abstract No 1A121 P]
[Text] A screen subassembly for a cathode-ray memory tube is proposed which makes
it possible to reproduce a moving semitone image with restoration of th~ standard
f ield frequency.
COPYRIGHT: VINITI, 1981
~1~~-2415~
19 -
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. FOR OFFICIAT. USE ONLY
ENERGY SOURCES '
_
LTDC 621.033.6.001.1 _
;
~ SOME ELECTROTECHNICAL PROBLEMS OF CONTROLLED THERMONUCLEAR FUSION -
Mescow ELEKTROTEKHNIKA in Russian No 1, Jan 81 pp 2-7 I`
� ~ academicians of the USSR Academy of .
(Article by P. Velikhov, I. A. Glebov, _
Sciences, V, A. Giukhikh, director of the iVIIEFA Institute imeni D. V. Yefremov;
[Text] Th~ solution to the grablem af controlled thermonuclear fusion is a most
~ i.mportant scientif ic research goal also having great social significance.
Large-sc?le physical research connected with the solution of this probl.em has been
pprformed in a numb er of areas for three decades, and it is continuing to be ger- ,
formed at the present time. As a result, we have succeeded in signifiaantly increasing
- the temperature, the den~:ity and the coafinement time of the energy in a plasm~ _
approaching the achievement of near-reactor parameters. It is possible
to consider that at this ti~ue all of the n~cessary physical pt~srequisites have been
created, and the corresponding engineering experience has been accumulated permi.t-
~ ting the design of a so-called demonstration thermonuclear reaction in the near
future in which the power engineering yield of the reaction will exceed the energy
spen~ on heating the plasma. For this purpose it is necessary to create large-
scale experimental devices, for the construction of which t'ne solution of a number ;
of complicated engineering problems has important signif icance.
At the present time more and more projects are developing .for the construction of _
the~next generation of devices. They must take the form of experimental thermonu-
clear reactors (TNR). In the TNR design and operating experience, it is necessary
to solve not only the physical and engineering problems of creating devices that
will function for a prolonged period of time while generating signif icant pos~er, but ,
~ also the economic, technological and other problems characteristic of industrial -
electric power plants.
The operating principle and the structural characteristics of the various types of
TNR have been discussed in considerable detail in the scientific and technical
- literature.
The study of the possible ways of creating TNR is proce~eding in two basic areas; steady-
state devices and pulse devices with magnetic or inertial confinement. _
The first area includes the tokamak type reactors, and the second, the A- _
pinch systems and reactors in which E:lectron beams and lasers are used f or heating
the plasma.
~ 20
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Example requirements on the reactor parameters appear in Table l. -
As examples Figures 1 and 2 show the schematic diagrams of the "Tokamak-20" devices
and a pulsed unit using the "Angara-5" relmtivistic electron beams.
The program for development of thermonuclear equipment is intersectional. Serious
problems must be solved by the electrical engineering industry. The electrotechnical
- praducts u~3ed in the in3icated units can be divided into three types.
The first type can include the standard general-purpose electrotechnical products.
The~e are systems for ~onversion of thermal power to electic power, pulszd capaci-
tors, thyristors, trans~formers for rectifying convertera,substation equipment, and -
so on.
The second type of product is the electrical equipment, which although it has proto-
types in electrotechnical devices, it requires developments as applied to the TNR
devices. Such products include powerful nonstandard thyristor units, capacitor
banks with increased energy capacity, electromechanical units for short-term
operation with inertial storage element.s, special transformers, inductive energy
storage elements, and powerful commutators.
I'inally, the third type of product is the experimental TNR devices themselves.
The purpose of this article is to define the basic requirements can the electro-
technical equipment, the solution of which to a significant degree determines the
5uccess of creating the next generation of thermonuclear devices.
- One of the prospective areas ir. this f ield is connected with tokamak type devices.
Some of the devices of this type that have been designed and built have the specifi-
cations presented in Table 2.
At the present time there are 30 large experimental units of this type operating in
the world (in tl~.e USSR there are 8) . New large units are being built: T-15 (the
USSR) , TFTR (the United States) , JET (EEC) , JT~60 , and so on.
_ For conversion to the production of industrial thermonuclear reactors with high
technical and economic parameters ~t is necessary to crea.te exper.imental engineering
devices and d�emonstration thermonuclear reactors on which th~ basic assemblies of
the future industrial reactors must be tested and developed. The design of such an
experimental device was begun with the participation of the USSR and on the basis of
international cooperation INTOR (the international tokamak) designed to obta.in
a thermonuclear reaction of several hundreds of inegawatts.
,
Let us briefly discuss somP of the electrotechnic al problens arising in the creation
of thermonuclear devices.
As is known, the conditions of confinement and hea ting of ~ piasma in a tokamak
chamber are insured by the mutual eff ect on it of strnng magnetic f ields created by
a system of large-scale windings. The toro:~_~.al winding creates a magnetic field
- which is directed a1Ung the plasma column, and p oloidal windings, magnetic fields
- perpendicular to it.
- The high intensity of the toroidal magn~etic field and the significant volume of the
ma~netic field, which is tens of cubic meters (for T-15) and hundreds of cubic
21 -
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meters (in the presently designed devices) and also a number of other factors lead
- to high complexity of the problem of creating the toroidal f ield system.
The theoretically required toroidal magnetic f ield can be created on the basis of
two diff erent technical solutions. One of them is based on the appl~ ation o� g
magnetic system formed by the usual type conductors and operating in the repeated
pulse mode. For excitation of this system it is necessary to have a short-acting
power supply with controlled valve converters with a power on the order of 500-1000
megawattsl. The second solution is based on the application of superconducting _
windings that create a stationary magnetic field, for the establishment of which in
a few hours it is necessary to have insignificant power of the power supply from
hundreds of kilowatts to several megawatts. Thus, the power required to feed the '
toroidal winding is reduced by hundreds of times.
For a T-15 device the version of a super-conducting magnetic systam has been adopted.
Characteristics of a Power System for a Superconducting Toroidal
Magnetic Field Winding T-15
Rated current, kiloamps 5
Time required to bring the current up to the maximum
value is regulated within the lisits of, hours 2-10 ,
, Power supply voltage, volts 750 ,
Energy output time constant under~emergency condi- ;
tions, sec 50 ,
Maximum voltage of the winding with respect to the
hausing in case of emergency lead-out of power, volts +1250 ~
~ The further growth of the requirements on the superconducting alectromagnetic system I
by comparison with the T-15 device is considered in the design of the new tokamak
type thermonuclear reactor.
~
. Designed En~r~y Parameters of a Thermonuclear Reactor
- Induction on the plasma axis, tesla 6
Maximum induction, tesla 12
_ Induction of the toroidal winding, henries 16
Power of th~ toroidal winding, joules 60�109
Height of the toroidal f ield coil, meters 12
Cycle time, seconds 1000
The analysis shows that the creation of a magnetic toroidal f ield system of reactors
of this scale without the application of superconductor engineering is economically -
inexpedient.
As the scale of the tokamak devices increasPs, the power and the energy reserves of
the feed systems of the poloidal f ield windings grow, and the operating conditions
become more complicated. A simple increase in power and energy of the devices us~d
previously to supply power to the poloidal field windings of the preceding tokamaks
1This technical solution is used as the basis for the large tokamaks built at the
present time in the United States, Western Europe and Japan.
22 _
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Table 1 ~
Charged par- Plasma Energy ca- Power supply Magnetic Working
Name of system ticle con- confine- pacity of power, P, f ield in volume,
- centration, ment time the power watts working v, ~13 ~
n, 1/cm3 sec supply, W, volume,
joules B, tesla
Quasi-stationary 5�1013-1014 10 1010 108-109 5-10 400-1000
- Pulsed with mag-
~
netic thermal
, insulation ~
Toroidal 6.-pinch 1016-1017 10 2 1011 10~3 12 10 300
- A-pinch with 1018 10 3 108-109 1011-10 30
linaX
Pulse with iner-
tial confinementl
Laser heating ~3�1~44 10_8~ 10~ 1016 10
El~ctron beam 10 10 10 1015 lU
heating
Table 2
Parameters of the device T-15 TFTR INTOR
Large radius of the plasma., meters 2.43 2.48 5.2
Small radius of the plasma, meters 0.7 0.85 1.3
Maximum plasma current, MA 1.4-2.3 2.5 1.3
Timz of existence of the maximum
, plasma current in each puls~, sec 5 1 100
Induction of a toroidal magnetic field
on the axis of plasma .coil, tesla 3.5-5 5.2 5.5
Maximum induction of the toroidal mag
netic f ield on the surface of the
winding, tesla 8 9.5 11
Ma.ximum power reserve of the toroidal
magnetic field, Mjoules 700 1000 40,000
Total power supply, 'megauratts 200 700 1500
Power of additional heating, megawatt 10-20 100 400
is unacceptable for technical-economic arguments, in connection with which the
necessity arises for the development of new systems and devices.
For supplying powex to the inductor circuit of the "Tokamak-15" device, the induc-
tive power storage elem~nt ar~~ the controlled thyristor converter are used. As the
storage element, the inductor winding is used in which electromagnetic energy is
- stored in advance, part of which is released in the plasma coil when the inductor ~
circuit is opened.
For realization of this power sysrem it is necessary to create unique dc switching
equipment which has a breaking power of 800 megavolt-amperes and a capacity of no
less than 104 responses and also electromagneic reversal permitting switching of
currents up to 80 kA in the inductor circuit.
23
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~
FOR OFFICIAL USE ONLY ~
. ,
_ / ~ ~ ~ '
~
, ~ ;
,
~ ~I~
. - - i iI
, II
~ ~ ,
1
~ ~
I
. ~ I ,
i
1
I .
Figure 1.
In connection with an increase in the duration of the existence of the plasma coil, ,
the problem of maintaining its equilibrium becames more complicated. In order to ~
solve this problem, a special equilibrium ~~ntrol system is provided; three windings
of this system are excited by the given progra.m which can be corrected automatically; :
two windings are f ed by the control system with feedback c=perating as a function of
the position of the plasma coi1. All of these windings are fed from controlled thyris-
tor converters. The power system has a total of 7 thyristor convertors with a total
. power of 160 megawatts.
- Now let us consider the peculiarities of the pulsed devices with magnetic confine-
_ ment of the glasma. For generation of electromagnetic fields in reactors by the
6-pinch type system with a liner, it is necessary to solve a number of complex
engineering problems, including the problems of creating magnetic systems of great
elongation and with high intensity of the magnetic field and the development of ~
pulsed energy sources with an energy capacity on the order of 1010 joules and a
pulse power of more than 1012 watts. The problems connected with commutation of
high power and preli.minary heating of the plasma. are highly complex ones.
Complex problems also arise in the development of reactor equipment with inertial
conf inement. In particular, for the method using high-current electron beams, it
is necessary to create a set of devices that generates a system of high-current
electron beams insuring comprehensive irradiation of the target by electrons with an
energy of 2-3 Mev and a total current i.n the tens of millions of amperes and with
~ a pulse duration of less than 10'~ sec.
The standard representative of these devices is "Angara-5." The "Angara-5" accele-
rator must provide for obtaining an electron beam with a total energy to 10 mega-
joules.
- The system is made up of a number of modules, each of which is a high-current elec-
tron accelerator. The basic part of the accelerator is the high voltage pulse
generatbr made up of two stages.
= 24
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25
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Table 3 ~ -
Specif ic Specif ic ~
, Storage element Area of ~
_ energy power, T, sec application '
- capacity, atts/g i
'oules/
Capacitive storage elements 0.03+0.0 102-~03 10 6+10 1 Pulsed systems ~
(0.1) (10 ) (10 ) with a power of ;
106-10~ ~oules ~
DC machine or AC unit with 1.0 0.2 1-10 Pulse sources ~
- rectifier (5.0) (1.0) 10a-109 ~oules
AC shock generators 1.5(10) 1-2(5-10) 0.01 Pulse sources
10~-108 ~oules ;
Homopolar generators (3--10) (0.1-10) Pulse sources
10~-109 ~oules '
Inductive storage elements 10-20 103-2�103 10-3-1.Opulsed and
(30-50) (5�103) ~ (10'S) ~quasi-stationary ~
~ sources
Note. The prospective values are presented in parentheses.
Basic Parameters of rhe "Angara-5" Device
Maximum electron energy, Mev 2
Electron current amplitude, Mamps 40
Pulse duration, nanoseconds 60-80
- Energy in the beam in 100 nanoseconds, Mjoules 10 '
Operating conditions Single pulses
The cap~citiye GIN [pulse volta~e t~enerator~] with a multiplication circuit b~ a voltage
~ of 2�10 volts and a pulse duration of 10- sec is used as the first stage. ~The pulsecharges
a high-voltage ~~i~ping lin~ with water dielectric. The discharge of th.e water
shaping line to pn ?lecrron source with cold emission generates an electron beam.
In connection with the future prospects of thermonuclear devices, the projects aimed
at the devplopment and the creation of the necessary experimental base and electric
power supply systems have great signif icance. Let us consider the basic types of
required equipment. The specif ications on the energy storage elements of various
types, the application of which can be expedient in thermonuclear fusion devices,
are presented in Table 3.
Each of the i.ndicatedtypes of storage elements is a separate scientif ic-technical
area.
Electromechanical Units with Flywheels. For analysis of the future prospects for
development in this area it is expedient to consider the requirements on the power
supply system in accordance with the design corresponding to the 1985 level of de-
velopment. For powering these devices it is proposed that a peak power of 1500
megawatts be used, including 300 megawatts from the network. The energy consumption
in an operating pulse is 5�1010 joules.
- ~ven under the conditions of operating several units in parallel, the indicated data
characterize the problems of improving the energy capacity of the flywheel [in the
existing units (0.8-1.5)�109 joules]. In the TFTR tokamak design (Unit~d States)
26 -
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provision is made for two units with energy stored in the rotating masses of the ~
~ rotors of 4.5�109 joules each.
High prospects are being opened up for the application of f lywheels made of synthetic
faaterials. Thus, for a steel flywheel weighing ].00 tons the stored energy wi11 be
109 ~oules; f or a flywheel weighing the same but made of high-strength light alloys
the stored energ~ will be 5�109 ~oules; flywheels made of prospective.composites -
will store 10�10 joules. The composites avatlable at the present time have a
specif ic strength which is many times greater than high-strength steel and alloy.
- However, the transition to the practical creation of such flywheels requires signi-
ficant efforta.
The provision of units designed to operate for short periods of time with synchronous -
generators does not seem to present any technical diff iculties at first glance, for
they are in the assimilated power range. However, the specif ic requirements of the
_ short-term loading conditions with variable rpm, the continuous fluctuations of the
currents in the stator and rotor windings make it necessary to create special ma-
- chines with increased resistance to such conditions. The development of shock
generators, in particular, generators with shorter pulses than the alternating cur-
~ rent halfperiod of 50 hertz appears to be prospective.
Inductive Storage Elements. For a number of cases the only eff icient power supply
can be an inductive storage element. As is known, the pulraed power supply based on..an
inductive storage element is a complex system consisting of the inductive storage ele-
_ ment itself, the devices for supplying power to it, the output system and the corre-
sponding auxiliary equipment.
One of the basic problems when creating a power supply based on an inductive storage
element is the development of a commutating unit.
The commutating units built at the present time have a breaking capacity to 1010
watts and an energy output time to load of tens of microseconds. The second stage
- of such a commutator is presented in Figure 3. The f irst stage provides the pro-
longed flow of current, and the second, fast breaking of the circuit. Destructible =
- elements are used as the second stage, in which the dc arc is extinguished using
oil, gas or dielectric (for example, paraffin) f illing the destructible gap. Three-
stage commutators are being developed which must provide for an energy transfer to
load time of several microseconds. Destructible foils and wires or destructible
' nonlinear resistances cooled to low temperatures are used as the third stage. The
superconducting commutating devices are of special interest.
Powerful Thyristor Converters. In order to supply power to the inductive storage -
elements, toroidal wind:Lngs of prospective thermonuclear devices of the tokamak
type, thyristor converters to voltage on the order to 3-5 kilovolts and a power to
= several thousands of inegawatts are required. In order to insure voltage division -
between the series included thyristors in this converter, series stage inclusion of
four valve sections is used. In order to limit the shortcircuit current in the
case of breakdown of individual thyristors, parallel inclusion of four valve stages
- is used. The adopted solution is awkward, and it cannot be considered optimal for
prospective converters. The development of prospective converters requires the
solution of a number of problems with respect to insuring current division between
the parallel valve sections and the protection of the individual valves and the con-
verter in the case of possible emergency shortcircuits in the dc modes and on
breakdown of individual thyristors.
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Pulse Capacitors. High-voltage pulse capacitors for electrophysical de~ices must
operate both in the vertical and in the horizontal executions at atmosphere and in-
creased pressures.
The operating conditions of the capacitors are as follows: aperiodic charge, oscil-
latary discharge, cycle repetition frequency no higher than 10 hertz. ~
The closest problems for the pulse capacitor version are as f ollows:
Improvement of the size and weight indexes (to units of 3oules per gram);
A decrease in inductance to 10-20 nanohenries;
Improvement of reliability;
A search for prospective dielectrics.
Cables for Electrophysical Devices. It is possible to note the following problems
with respect to the creation of new cables:
Improvement of the rated cable voltage to 200 kv;
Reduction of the cable inductance from 200~300�to 30-50 nanohenries/m (with a simul-
taneous increase in cross section).
m zso
Figure 3.
High-Voltage Electrical Equipment. The power supply systems for the engineering
complexes of thermonuclear reactors also consist of a large number of power subsys-
tems of individual ionic sources including high-voltage, high-current electric: power
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aupplies which are under high potential relative to ground and powerful high voltage
- power supplies for the accelerating electrodes of the ion sources.
The high-voltage electric power supply systP..ms of ion sources have been developed
for the following output parameters: Urect - 150 to 200 kv; Irect - 100 to 120 amps;
output voltage stability considering pulsations 2-3% with buildup time to the rated
value and discharge of it to zero under emergency conditions of no more than 20-30x
10-6 seconds. The output parameters of high-voltage electric power supplies are as
follows: UO1t = 20 to 100 volts; Iout - 3 to 6 kiloamps; output voltage stability
coasidering pulsations no worse than 0.5-1y.
The creation of electric power supply systems for the engineering complexes of
thermonuclear reactors can be realized with the participation of enterprises of the
electrotechnical industry in the development of the following electric power supply
equipment elements;
High-voltage, step-up transformers transformers with a capacity to 400�106 volt-
amperes, insulation class 150-200 kv, with insulated neutral, for operation on high-
voltage control]able rectifiers for an output voltage, of 150-200 kv with a power _ _
to (250-400)�lOd watts with the capability for outdoor installation;
High-voltage, high-speed commu~ators based on vacuum arc-suppressing chambers for
protecting the ion sources and the electric power supply system equipment during
emerg~encies, for a commutatable current of 100-200 amps and operating voltage to
200-250 kv; -
_ Powerful high-voltage generating triodes operating in the switching mc,de capable of
switching circuits with a voltage to 250 kv for a prolonged operating current of
100-150 amps.
Superconducting Windings. The design and manufacture of large-scale superconduct-
ing magnetic systems has specific difficulties. For high inductions, significant
ponderomotive forces acting on the winding and variable poloidal magnetic fields
there is a danger of transition of the individual sections of the superconducting
winding of a toroidal field to the normal state. This can be avoided by selecting
the required reserves, for which it is necessary to use alloys with given proper- _
~ ties as the current-carrying element. It is necessary also to insure winding
strength under the effect of electromagnetic forces, sufficiently effective liquid-
helium cooling, the output conditions of high energies on transition of the coil
to the normal state. In the case of emergency transition of a superconductir.g
winding to the normal state, the protection system must respond, and energy is out-
put from the winding to the external load, for otherwise damage to the winding is
unavoidable.
The superconducting toroidal field winding (SOTP) must be resistant to the effects
of variable magnetic f ields created both under operating conditions and on breaking
the plasma current. The SOTP of the T-15 device consists of 24 superconducting
coils placed in powerful stainless steel housings. The base for the superconductin$
coils is a superconducting current-carrying element, which is in the form of a
transposed system of composite, multi-strand Nb3Sn-canductors with two copper pipes, _
connected to it for circulating liquid helium. Each coil consists of six two-layer
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~
disc coils placed in a strong stainless steel housing~ In order to fix the posi- '
tion of the coils of the toroidal f ield Windings and pick up the loads from the
tipping moments, fastenings are provided that insure strong mechanical bindings -
betWeen the individual elements of the toroidal f ield windings. _
j
In conclusion, it must be noted that although the final form of the thermonuclear
reactors has still not been developed, it is possible to define the basic electro- '
technical problems arising in making the transition from plasma physics
research to reactor building engineering. As was demonstrated, the electrotechnical
support of experimental and, subsequently, experimental-industrial thermonuclear
devices is a complex scientif ic-engineering problem. Its solutions are connected
with the improvement and efficient application of standard electrical equipment,
just as with the design and the production of complex nonstandard equipment on which
very high requirements are imposed. This requires a large volume of scientific re- -
search work and the creation of a special experimental base in the electronics in-
dustry.
COPYRIGHT: Energoizdat, "Elektrotekhnika", 1981
[161-10845]
10845 -
CSO: 1860
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UDC 621.318.3:621.039.5.U01.4 _
ELECTROMAGNETIC SYSTEMS OF TOKAMAKS
Moscow ELEKTROTEKHNIKA in Russian No 1, Jan 81 pp 7-16
[Article by I. F. Malyshev, N. A. Monoszon, doctor of technical sciences, N. I.
Doynikov, candidate of physical and mathematical sciences, A. I. Kostenko, B. V.
Rozhdestvenskiy, Yu. V. Spirchenko, G. V. Troki~chev, G. F. Churakov, candidates ~~f
technical sciences, V. P. Muratov, engineer] -
[Text] The electromagnetic system (EMS) is one of the basic systems of the tokamak.
It generates magnetic and eddy electric fields providing for the formation, active _
heating and confinement of the plasma in the discharge chamber, the thermal insula-
- tion, stability, configuration control and control of spatial position. The mag-
netic field can also be used to purify the plasma of the thermonuclear reaction pro-
ducts and impuritiesgetCing, in from the first wa11, protection of the latter from
the particles emitted by the ~,lasma. The qua.lity of the magnetic f ield has a sig-
nificant influence on the plasma characteristics.
From the engineering point of view the electromagnetic system is a complex electro-
technical device characterized by significant electrical, magnetic, mechanical and
thermal loads encompassing the discharge chamber, blanket and sh,i:elding and provid-
ing access of the particle beams, energy fluxes and diagnostic means to the plasma.
The problem of creating the electromagnetic system is greatly complicated when de-
veloping the tokamak thermonuclear reactors as a result of the necessity for apply-
ing superconducting windings in this case which completely encompass the hot zone of
the reactor the discharge chamber with the blanket and shielding and the necess-
ity f or operational servicing of this zone without dismantling it for long interrup-
tion of the normal opera~ion of the EMS [electromagnetic system]. -
- The indicated ar guments determinethe necessity for developing special structural
designs and calculation techniques providing for the possibility of creating EMS
for experimental devices and the thermonuclear reactors of tokamaks.
Electromagnetic Syste~as with Normal Windings. The structural diagram of the EMS
w-ith closed ferromagnetic circuit is shown in Figure 1. The EMS is a pulsed trans-
former in which the toroidal discharge in the vacuum chamber is created by an eddy
electric field, and the plasma current in the discha.rge chamber is the secondary
, shortcircuited coil of the transformer. In order to suppress the main magnetohydro-
dynamic instabil ities of the plasma, the powerful longitudinal magnetic f ield of the
toroidal solenoid is used, inside which a vacuum chamber is located.
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The annular plasma coil striving to expand under the effect of the electrodynamic
forcea in Lts own magnetic f ield and the gas kinetic Pressure is kept in equilibrium by ~
_ meane of an external poloidal magne~ic field. The basic source of the eddy emf is
the inductor winding (OI). In the window of the transf ormer, in addition to the
toroidal field winding (OTP) and the OI, there can be control windings (OU) gene-
rating poloidal magnetic f ields determining the shape of the transverse cross sec-
tion of the plasma column and maintaining its equilibrium and also auxiliary w~Cnd-
ings remagnetization, induction heating of the chamber, and so on.
. J 2 3 4 S.
r e o
. o ~ ~ ,
1 6
- 8
\ .
- Figure 1. Structural diagram of the T-3. 1-- OTP [toroidal f ield
winding]; 2-- magnetic circuit; 3-- OI [inductor Winding]; 4--
OP [remagnetization winding]; 5-- KO [correcting winding]; 6-- OIN
[induction heating winding of the chamber]; 7-- OI shields; 8--
_ plasma shields; 9-- discharge chamber ~
In the first experimental devices with short duration of the operating pulse for
_ maintaining equilibrium of the plasma, a copper shield located in direct proximity
to the plasma boundary was used. If the operating pulse duration is less than the
time of diffusion of the magnetic field through the wall of the shield, then when
the plasma approaches it, eddy currents ar e induced in the shield creating fields
which equalize the forces def orming the plasma coil. The electromagnetic systems of
- the f irst tokamaks were developed at the IAE [Nuclear Power Institute] imeni I. D.
Kurchatov, at which, as is known, the tokamak system was proposed.
The developments of l.arge experimental devices requiring the solution of an entire
- series of engineering problems connected with the creation of electromagnetic sys-
tems and the broad involvement of industry for the manufacture of electrophysical
- equipment were started at the end of the 1950's. The basic parameters of the elec-
tromagnetic systems of these devices are presented in the table.
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Basic parameters of electromagnetic systems
EMS parameters Type of device
- '"-3 T-3A T-4 T-10
, Large radius of the torus R~, 1 1 0.9 1.5
m~ters
Plasma cross section radius 0.21 0.21 0;2 0.35
a, meters
ifaximum induction of the lon- 4 4 5.4 5
gitudinal field on the ra-
dius Rp(B tesla "
Total varia~ion of the magnetic 2 2 1.7 4.3
flux of the inductor ,W-sec
Time of maintenance of tni maxi- ~�2 0.3 0.3 1
mum longitudinal f ield t, sec
OTP energy reserve W~, megajoules 25 25 45 130
Peak power of the OT~ feed PT, 77 77 77 180 -
megawatts
Energy of the capacitor bank 2.2 2.2 2.2 5
feeding the OI, W~g, mega~oules
Induction of the OU--on a radius Q.~25
R~, tesla -
Mass of the active steel of the 105 105 100 230
magnetic circuit, tons
- Mass of the winding copper, tons 25 ~ 18 10 60
Year of development 1959 ; 1963 1965 1971
The T-3, T-3A, T-4 devices were built for experimental studies of a plasma with
short duration of the operating pulse (on a scale of 100 milliseconds or less) and
differing little from each other with respect to the EMS designs. Their structural
diagrams are analogous to that presented in Figure 1. _
The electr~magnetic system of the T-3 consists of a magnetic circuit, the toroidal
f ield winding (OTP), inductor winding (OI)! remagnetization winding (OP), the cor-
recting winding (KO) for correcting the transverse fields and the induction heating
winding of the chamber (OIN) which heats it to a temperature of several hundreds of
degrees to degas the walls. The plasma current buildup during development of annu- -
lar discharge and active heating of the plasma are insured by the variation of the
magnetic flux ~~i in the ma.gnetic circuit.
In order to decrease the sizes of the OP and the f eed power, it is desirable not to
permit strong saturation of the magnetic circuit. The remagnetization of the latter -
before the beginning of the operating cycle permits the solution of this problem and
an increase in ~~i and the duration of maintenance of the plasma current. On the ~
T-3 device the magnetic circuit is remagnetized from B1 =-1.8 tesla to B2 = 1.8
tesla. The most responsible part of the magnetic circuit is the core. As a result
of limited space, it is used as the supporting column for the OTP coils, and it
takes the loads from the force of radial compression of the OTP.
For the tokamak EMS, structural designs of cylindrical monolithic cores were deve-
loped from bonded sheets of electrotechnical steel capable of reliably taking
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significant mechanical loads. The OTP of the T-3 device creates a magnetic field ~
in a toroidal volume of 2.21 m3 with induction of B~ = 4 tesla on radius of R~ ;
and maximum induction on the winding Bl = 6 tesla. It consists of 8 OTP coil
modules uniformly arranged along the azimuth with relatively small gaps between
them. In order to reduce the f eed power, decrease the mechanical stresses and tihe '
heating of the OTP, a great deal of attention has been paid to improving the coeffi- ~
cient of f illing of the winding with copper. For this purpose, the se~tions with -
coil insulation were warked into a wedge and made monolithic.
The OTP coils are subjected to the effect of signif icant radial tensile forces
caused by interaction of their currents with their own field. Asa resultof toroidality,
the specific pressure from these forces is distributed r_onuniformly with respect to
the OTP coil circuit, and in the T-3 it varies from 3.6�10~' to 14.4�106 Pa. This
nonuniformity in the pressure distribution causes bending moments that act in the
plane of the coil and try to elongate it vertically and give it a D-shape. However,
the geometric dimensions of the T-3 and the magnetic =ield level still do not reach
- values such that the strength problems acquire extraord3nar ily great significance.
When investigating the stress-strain state of the OTP, along with the forces acting
in the plane of the coils it is necessary to consider the f orces caused by interac-
tions of the OTP currents with poloidal f ields generated by the plasma currents and ,
- the polodial windings. However, in the T-3 these forces are small as a result of -
attenuation of the penetration of the plasma current f ields into the OTP region us-
ing shields and an insignif icant level of the OI and OP scattering fields.
When investigating the problem of the mechanics of the EMS, it is also necessary to
consider the ponderomotive forces in the screens. The fact is that the copper _
screens must have insulating jvints in the radial planes of the torus in order to
= avoid shortcircuiting by the screen of the eddy emf. Thus, the screen must be made
of individual sectiors insulated from each other azimuthally, on the ends of which
the eddy currents maintaining plasma equilibrium are closed. The end currents that
flow across the powerful toroidal field cause ponderomotive forces which must be _
considered when developing the structural designs for the screens.
Rigid requirements are imposed on the quality of the toroidal field. The tolerances
- on the transverse f ields at the beginning nf the operat~ng cycl~ in the region of
formation of the plasma coil are within the limits (10 to 10 )3~. The sources
of the transverse f ields are the inaccuracies in the manuf acture and installation
of the OTP coils, the fields of the intercoil connections, and the scattering f ields
of the poloidal windings. On the T-3 device the primary source of transverse fields
is the remagnetization winding. The calculations and exper imental studies demon-
strated that for corresponding placement of it in the window of the EMS, these
tolerances can be maintained. In order to lower th~ transverse f ields from the OTP,
the ad~acent sections are wound in opposite directions with the formation of bi-
filars from the connecting links.
The next step in the tokamak research program was the creation of the T-10 device
with large volume, current and duration of the plasma conf inement. The T-10 de-
~ vice is among the largest operating tokamaks in the world. In order to optimize the
T-10 parameters, a computer program was developed permitting an analysis of a large
number of versions considering the physical requirements and the characteristic
- features of the structural design. On the '~asis of the perf ormed analysis, a ver-
sion of the device raas selected with the following basic parameters:
34
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Large radius of the torus R, meters 1~5
Sma11 radius of the plasma ~ross section,
- a, meters 0.35
Plasma current I P1, Mamps 0.8
Duration o.f the bperating pulse ti, sec 0.8
~ The general view of the T-10 and transverse section of the EMS are presented in Fig-
ures 2, 3. The basic dzfferA ices in the structural design of the EMS of the T-10
from the T-3 ai:d T-4 consist in the following;
In connection with incr easing the duration of the operating pulse f or stabilization ~
_ ;,f tr.e position of the plasma, along with the copper shield, the OU is used;
In order to improve the uniformity of the OU f ield and decrease the total mass of
the device, the magnet ic circuit is made four-yoked instead of two-yoked.
The strength problems were complicated significantly on the T-10 device. The total
radial force of compression of the central core by the toroidal field winding on
tlie T-10 reaches 1.1�10 $ idewtone. The induction of the toroidal magnetic f ield
inside the OTP varies within the limits of 3.7-7.9 tesla, and the pressure on the _
winding varie~, correspondingly, within the limits of 5.5�106 to 25�106 Pa. In
addition, as a result of interaction of the OTP currents with the OU f ield, signi-
f icant tipping moments appear which try to turn the OTP modules araund the lines of
intersection of their midplanes with the median plane of the device. The magnitudes
of these tipping moments reach (8-~10) �105 N-meters.
Electromagnetic Systems of Experimental Devices with Superconducting Windings. The
estimates show that the economical thermonuclear reactors of the tokamaks must have
powers on the order of 109 watts per unit and operating pulses with a duration on
- the order of 102-103 sec. This requires the conszruction of EMS w3.th volumes of the
toroidal field on the order of 103 m3 and electromechanic energy reserves of tens of
gigajoules, or nore. Tlze total pulse durations d~ not permit restriction by the
passive screens in order to maintain equilibrium of the plasma column. For this
purpose it is necessary to use OU controlled by automated control systems. Reactor
c~iS with ~ceptabie tecanical-economic characteristics can be built only on the basis
_ of superconductors. The large scales and harsh operating conditions make the
problem of creating sup erconducting electromagnetic systems (SEP~iS) for them which
are subject to the eff e ct of variable poloidal magnetic fields during operation un-
der enormous mechanical load~ extrAmely comple~c. Its solution can be obtained
only as a result of the construction and the investigation of a number of experimen-
_ tal devices. A number of programs have been planned for this purpose. In our coun-
- try provision has been made for the creation of tokamaks using superconductivity.
In the United States, along with the construction of tokamaks with superconducting
windings, a large exper imental device is b~ing built with superconducting coils of -
dxfferent types for the OTP (LCP large-coil pro~ect).
The .first experimental installation of a tokamak T-7 with superconducting OTP in
the world was developed and built at the IAE imeni I. V. Kurchatov Institute with
' the participation of the "Kriogenmash" NPO [scientific production association]
- [see reference 1]. At the end of 1977, the OTP of the T-7 device was installed and
tested, confirming the correctness of the basic technical solutions used in its de-
velopment.
~ 35 -
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~
t ,
~ ' ' -
~
. ~
~ '
- ~ ~
~
~ ~ -
_ ~ ~ -
~ ~ s~ ~ ~
~ ~ � ~
~
~ ~ oe _
o ~
~ � = ~
0
: f: ~
'
~ ~ f ~ l-
~ 1 , ,
~ ~
�'N'~ ~~'~l~ ~
i\~ ~
. y~ ~
- ~ v
~ ~ ~
~ ~ ~ f
~ ~ ~ ~ ~
~I ~
~ -
Figure 2. General view of the T-10 tokamak.
Basic specif ications of the T-7 -
Large radius of-the toru5 R, meters 1�22
Small inner radius of the~chamber ak, meters 0.35
Toroidal field induction BQ, on the radius
Rp , tesla 3
Maximum induction on the OTP B, tesla 5
~ Electromagnetic energy reservemof the 20
- OTP, Mjoules 1
Operating pulse duration ti, sec
~
~
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- In order to maintain the plasma equilibrium, a liquid nitrogen~cooled, copper shielc
was used which is able to greatly reduce the penetration of the plasma current
- field into the OTP region during the operating pulse, and at the same time, to de-
crease the neating and the tipping moment of the OTP. At the present time a larger
experimental T-15 thermonuclear device was designed with superconducting OTP and
liquid nitrogen-cooled OI 3nd OU. It is designed to obtain and ~tudy a plasma with
parameters approaching thermonuclear and solve a number of engineering problems con-
= nected with the creation of power engineering reactors.
In the initial stage of design, provision was made for obtaining a magnetic f ield
of ~iQ = 3.5 tesla on the radius Rn= 2.4 m, with the help of the superconducting
wind3ng of the toroidal field (SOTP) on the basis of Nb-Ti [see reference 2]. The
_ magnitude of the plasma current IP1 = 1.4 Mamps, and the durati~n of the operating
pulse ti = 5 seconds.
~ I 6 S 4~ .
~3000
_ ` ~/0'40 I
I
r ~~szo ~ z
I .
,
- I ~iJeo ~
~ , ~ i
_ ~ _ - ~ ~-~o _ ~ _ , ~
~ a~s
4~~d5 I ,
' I
. ~ ~
i
~ - - , ~ ~~io~o ~
~
- i i~.
.
- i ~
_ ~ ~ ii
Figure 3. Electromagnetic system of the T-10. 1-- OTP; 2-- outer
coil of the OI; 3-- inner coil of the OU; 4-- induction heating
winding; 5-- remagnetization winding; 6-- OI.
~
. In order to decrease the urol-ability of the transition of the SOTP coils to the nor-
mal state, a shape elongated vertically and approaching the momentless conf iguration
was selected for them, and provision was made for putting the OU inside the OTP.
The momentless configuration permits the mutual displacement of the winding elements
- 37
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u~der the eFfect of the ponderomotive forces to be diminished, and it permits a
~ reduction in the probability of transition of Che SOTP to the normal state on
- excitation of the toroidal field. The placement of the OU inside the OTP signifi-
cantly reduces the induction of the pulsating poloidal field in the vicinity of the
OT? by comparison with the outside location and the heating of the tilting moments
caused by them. It is possible to include the complication of the manufacture of
the equipment, assembly and dismantling of the device among the def iciencies of
the momentless conf iguration and pl3cement of the OU inside the OTP.
In connectior. with the progress in ID.astering the production of combined multistrand
- superconductors based on Nb3Sn and +che experimentally demonstrated possibility of
manufacturing SEMS from them with magnetic f ield level and mechanical loads charac-
teristic of large tokamaks [ref. 3],the decision was ma.de to use the Nb Sn-based
superconductor having lower sensit3.vity and thermal disturbances as a result of the
higher critical temperature for the OTP of the T-15. This made it possible to con-
vert to the circular shape of OTP coil and outside placement of the basic OU instead -
of the previously adopted momentless shape of Che OTP coil and the inside placement
of the OU, the manufacture of which causes defined difficulties. Here the theore-
tical possibility of forcing the operating conditions of the T-15 is manifested,
increasing the induction in the center of the plasma cross section to five tesla
and the plasma current to 2 Mamps.
The technical s~ecifications of the T-15 device (the rated parameters are presented
in the numerator, and the expected parameters under forced operating conditions are
- indicated in the denominator) -
Large r~.dius, meters 2�4
Small radius of the plasma column
(with respect to the diaphragm), m
Toroidal magnetic field induction on 3.5/S
the axis, tesla
Maximum nonuniformity of the toroidal +1%
_ field in the vicinity of the plasma 2.5
Stability margin at the column boundary
- Total variation of the magnetic flux of 15/17
the induc.*_or volts-sec
- Admissible induct~on of the poloidal
f ield ir the vicinity of the plasma
for I 1= 0, tesla 10-3
rlaximumpplasma current I 1, Mamps 1.4/2.0
Buildup time of the plas~ia current, sec ,
to i 1= 0.14 Mamps 0.014
to IP1 - 1.4/2.3 Mamps 0.614/1
- Duration of the plasma current pulse, sec 5
_ Pulse repetition frequency under the rated
operating conditions 1 pulse in 10 min. -
Additional heating power introduced into the
plasma using microwaves or injection of -
the neutrals, Mwatts 10
Figure 4 shows the general view of the T-15. The EMS includes the closed ferromag-
netic, 12-yoke magnetic circuit, SO'TP, OI and OU, liquid-nitrogen cooled, and the
38
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thermal induction heating winding o� the OIN chamber installed on the core. The
EMS together with the discharge chamber located inside the SOTP is placed in the
common vacuum-sealed housing (cryostat). Thus, the devices placed inside Clie
EMS housing in the operating state are maintained on different temperature levels:
For a temperature of T-4.5K SOTP with adj acent power structures to it;
At a temperature of T~ 80 K-- OI and OU;
At a temperature of T~ 300 K-- magnetic circuit, OIN, discharge chamber, EMS
_ housing.
In order to decrease the thermal fluxes, the internal space of the EMS housing is
_ ev~acuated to a pressure of 1.3�(10'3 to 10-4) Pa, and radiation shields cooled by
liquicl nitrogen are installed between the regions with T~ 4.5 K and T~ 300 IC. In ~
contrast to the T-3, T-4 and T-10, the T-15 does not have a remagnetization winding. -
Before the beginning of the operating cycle in order to decrease the variation of
the inductor flux and the duration of the operating pulse, the magr_ztic circuit
is remagnetized using the OI to powerful saturation of the core and ~n the initial
stage of formation of the plasma, it is used as the inductive energy storage element
to insure a fast rise of the plasma current. The SOTP consists of 24 large super-
conducting coils placed in the stainless steel suppor~ing housings, 3oined in.pairs
in 12 mounting modules. The positioning of the coils along the ra3~.us is fixed by
- the central supporting column made in the form of a cylinder with two insulating
= joints vertically. The central cylinder takes radial forces of 1.2�107 Newtons
from each coil. The superconducting conductor (Figure 5) is a transposed system
of composite superc~,lductors with two copper tubes connected to it for the
cooling helium circulation. The structural design and the parameters of Che cryo-
genic system provice for the possibility of cooling both by transcritical and two-
phase helium.
The SOTP coils are series cunnected and have four pairs of current lead-ins which
exit through the EMS housing and divide the entire winding into four sections. The
sectioning permits an eightfold decrease in the voltage of the winding with respect
to ground by comparison with the total voltage acting in the SOTP circuit on output
of the energy of the magnetic field to the external discharge resistances, which
occurs for protection of the winding in case of transition of it from the supercon-
ducting state to normal. The loads from the tipping moments are taken by the central
column and special structural elements which provide strong mechanical couplings be-
= tween the individual elements of the SOTP.
The choice of the number of coils and the inside dimensions of the SOTP coil is made -
by the structural arguments and the tolerance on the nonuniformity (corrugation) of
the magnetic flux at the edge of the plasma. Corrugation is c~used by the presence
on the outer radius of the toroidal solenoid of large gaps bet'~aeen individual coils. _
- For calculation of the magnetic fields and ponderomotive forces of the SOTP, it was
necessary to solve a three-dimensional problem.
The basic OU provided for maintenance of plasr~a column equilibrium and the calcu-
lated shape of its transverse cross section are located outside the SOTP. They con-
sist of three pairs of circular coils made of an aluminum bus with a hole for liquid
nitrogen circulation. The coils are fastened to the radiation shields. The spatial
- pattern of the f ield and its variations.with time are calculated considering the
39
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~ ~t7901>
p1 ~BOO ~
' ,
~ ' + + : + t -4~
~ +
, ~ .
,
Illu~~~ ~~~~ql _
,
,
v
,
_ \ .~40~ ~ ~ _
_ - ZG. N h
,
i
, ~
Ilu~~~� ~~~~IIII ~
~ ' . + r ~
~ -f-~ ~ ~ ~ + ~ ~
l.._J l~~ ~ ~ I
. ~;Jr.:y. K~i. ,
. ' I /
Figsre 4. General'view of the T~15. 1--- inductor windings; 2--
current lead=ins;3 control windings.
I~iD c;L the plasma equilibrium and variations of its active and inductive resistances,
gas kinetic pressure and saturation of the maanetic circuit during the operating `
pulse. The OU currents vary by the program and are c~rrected by the feedback system.
The fast variations of the plasma position are corrected using the high-speed con-
trol winding (BOU) placed between the 50TP and the discharge chamber in direct proxi-
mity to t~e plasma The BOU is designed to generate fields with an amplitude of about
= 0.015 tesla with maximum variation rate of the field of 5 tesla/sec. The varia~'
tions of the poloidal magnetic field during normal operations of the device do not
lead to dangerous heat releases in the SOTP capable of causing its transition to the
normal state.
Harsher operating conditions of the SOTP arise on cutoff of the plasma current. The
plasma current cutoff can lead to uncontrolled tran~ition of the SOTP to the normal
state as a result of its heati.ng caused by losses of electromagnetic energy and due
to fast variations in the induction dB ~n the vicinity of the superconducting con- `
ductor. Figure 6 shows the calculated magnetic field patterns before and af ter
- cutoff of the plasma current in the rated mode. The solid lines correspond to
const before cutoff, the dottied lines, to const after cutoff.
40
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From Figure 6 it is obvious that the largest value of dB is reached in the maxi-
mum induction zone of the toroidal magnetic field, that is, in the region with
minimum reserve with respect to kinetic temperature. In the rated mode ~B =0.48
= tesla, and in the forced mode 0.69 tesla. The specific heat releases q on
variation of the induction in the conductor are defined by the expression,
~oules/m3 _
z
(oe~
q=k ~
2Fie
. where k is a coefficient which depends on the variation rate of ~B and the charac-
teristic damping time of the eddy currents in the conductor.
1 2 ,T -
~ ~
~ o
.
h -
b
i _ IB_J .i _
~'r . ~f~.
Figure 5. Superconducting conductor of the T-15. 1-- copper; 2--
Nb3Sn in a bronze matrix; 3-- cooling channels.
CM Z
250 - ~'=~'~`ZrB-c , (a)
~
0,2"Z.rc'
- - Ccycaue C~C
~?3=1n' _ - _ - , - !
~ ~ Q B 7 6 ~
0, 4'~2Yt ~ , - - - ; v~~ ,~~5
ZOO i ~ ~ ~ " r ~ J ~ rC N ~ ~ ~Z'1rt +
~ ' ~ ~(0.I/OMA1 ~ , o J,J'~1T' ~
0,5xZr iJ,1BSn+A~1 0'0 0,~ I + O,f~26,NA(0,?!l.N~) ~Q -
!50 ~ ~ i + g ~ ~C ~ 06 ~O,I Zn, ~
~ \ ` 5` ~ is ~~~Zr =
~r ~
~ ~ ? + ~ \ 1 ~ ~ ~ ~ i , Sx 2r
I ~ ,`o 0 0, 5 ? / I,swt~~ ~
~ . ~
I00 ~ + � o ~ 8~ ' ~ ~ i7x?r
~ + ~ ~ -a3~ir , ~ i ~ ' ~ /~6~q
A
+ ~ ~ rt Z~y ` ~ ~
50 ~ ~ a~ ~ _,~~6
I ~ I t ~f Jx ~ ' 1 r
~ ~ ~ + ~ ~ a~a a ~ i ,
R
p 50 +/00 '!SO 200 150 . J00 J.fO y00 4~50 cM
Figure 6. Poloidal f ield pattern of the D-15 plasma current cutoff =
in the rated mode. _
Key: a. C-C section
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For instantaneous variation of the f ield k= 1. With an increase in the duration
of the variation of ~S by comparison with the characteristic damping time the value
of k decreases. The calculations demonstrated [4] thatin the rated mode the current cut-
off even with the time constant less tilan 2�10'"2 sec must not lead to transition -
of the SOTP to the normal state. However, in order to prevent the ].atter in the
forced mode it is expedient artif icially to increase the time constants of the
SOTP coil housings in order to slow the variation of ~B.
As a result of the fact that Nb3Sn is characterized by increased sensitivity to
- deformations, insurance of high rigidity of the structural element.s and development
_ of reliable methods of calculating its stress-strain state are very important. A
calculation was performed by the finite element method. The basic assumptions
made for the calculation were checked experimentally. In the developed structural
design the total deformation of the superconducting conductor taking into account
the effect of the ponderomotive forces and production technoZogy is about 0.3%.
Figure 7 shows the stress intensity distribution and the displacement of the outer
- circuit of the SOTP module from the forces operating in tha plane of the module in
the forced mode.
From Figure 6 it is obvious that on cutoff of the current, induction components
occur that are perpendicular to the direction of the current density vectors in the
= coils of the OTP and caus e the appearance of tiFping moments. Thus, the maximum
tipping moments occur during cutoff of the plasma current.
I
_ In the T-15, tl~e tipping moment for cutoff of the plasma current in the forced mode
will be 3.6�lOd N-meter on the coil.
Basic technical parameters of the EMS of the T-15 device
TorQidal field winding
Number of coils 24 -
Induction from the radius R0, tesla 3.5/5
Maximum induction with respect to the
winding, tesla 5.8/8.3
Magnetic f ield energy reserve, Mjoules 380/750
Operating current, amps 3600/5200
Superconducting conductor:
Nb3Sn cross section, cm22 0.1
copper cross section, cm 2 0.8
cooling channel cross section, cm 0.14 3
_ mass, kg 90�10 -
Maximum stress in the SOTP circuit with
protected magnetic f ield energy output, kv 12
Time constant for energy output, sec 20
Radial force on the coil, iJewtons 6�106/~.2'10~
Tipping moment of the coil, N-m 1.6�10 /3.6�106
Weight, tons 300
Cooling system circulation, trans-
critical or two-phase _
helium for T= 4.5 K
Heat release at the level of about 4.5 K:
stationary, watts 1250
pulse, joules/pulse 150/270 4
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Inductor
M,aximum magnetic f lux, W-sec 7~5
Maximum induction in the core/yoke, tesla 3.3/1.25
Total current of the OI, Mamps ~5.5
Energy reserve of the OI, Mjoules 7
OI voltage, kv g
Maximum current of the OI, kiloamps 80
Energy losses in an operating pulse, Mjoules 7.8
Weight of the magentic circuit, tons 750
Weight of aluminum in the OI, tons 4 -
_ Control winding
Vumber of basic OU 3
ilumber of BOU
Total current of the OU, Mamps 1.5
Total current of the BOU, Mamps 0.07
OU voltage, kv g
- BC~U voltage, kv 3
Energy losses in the working pulse, Mjoules:
OU 15.5
BOU 2 �
n,za
a~f -1- c- _ Q09
' /~SO 7S0
iS0 ~ ~
4~~ _ 71J0 7.~
I ~
s SO 7S0
~ r~na
izso
JJ00
~ I7S0 � S00
1R~0 130 ,
~ l000
~ 1250 ~ -
IS00
406 ~1AA1 I7S0
- - - , ~ g~s
Figure 7. Intensity distribution of the stresses and displacements
of the outer circuit of the SOTP module from the forces acting in
the plane in the forced mode. stress intensity isolines;
displacements.
Electromagnetic Systems of the Reactors. An idea of the scales and problems of
building reactor EMS can be obtained by the materials from the design developments
of these devices [see reference 5]. As is known, the final goal of the program with _
respect to the problem of controlled thermonuclear fusion is the construction of
thermonuclear power engineering based on "pure" thermonuclear reactors. However,
the creation of hybrid thermonuclear fusion-fission tokamak reactors (G~TRT) wizh
- a uranium blanket [5] designed for plutonium working and electric power production
is of great practical interest. The building of these reactors requires the solu-
tion of the same basic problems as the "pure" reactors, but in facilitated form
(high plasma parameters and neutron loads on the "first wall" are not required, and .
the dimensions and thermonuclear power can be reducEd signif ~cantly). In Figure 8
a diagram of the transverse cross section of a 6900 Mwa.tts thermal power GTRT is
43
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shown from the materials of the very beginning developments. The structure of the
EMS is obvious in this diagram. In contrast to the T-15, the plasma has a verti-
cally extended transverse cross section which is more advantageous with respect to
the physical parameters. Obtaining high economic indexes and sufficiently positive
service life require the use of operating pulses on the order of hundreds or more ,
seconds long (for the GTRT, t. ~ 1000 seconds). For such pulse durations at the
present time it does not appear possible to get around the divertor which permits -
the products of the thermonuclear reaction to be pumped out of the discharge chamber,
protection of the wall of the discharge chamber (the first wall) from destructive
bombardment of it by particles emitted by the plasma and also a decrease in the
- flow of impurities from the chamber wall.
In order to obtain a noncircular, vertically extended plasma cross section it is
necessary to generate external multipole poloidal f ields~ Here the separatrix of
the poloidal field is formed with one or two zeros, and the most natural is the
application of the poloidal d iverter. This diverter was provided in the G~RT. -
- Figure 9 shows the calculated pattern of its magnetic f ield formed by the SOU
located both outside and inside the SOTP. The charged partieles go from the outer
diverter layer of the plasma moving along the magnetic lines of force to the diver- -
ter chambers where they collide with its walls, are neutralized and pumped out.
- _ _ . _ ,
. _ _ ~
. ~ '~~~'111~1w�~ - ~
1 a ~
~ ~ � ~
; ~ ~ ~
. ~,,a ~ ~~~i ~ .,,~t ;
; ; ~ 1 ~i - ~ ~ ~ ;
- l. ~
~ t~ s o
r' r. . f
~ iW� ' I
I ~
.
~ _
�
t _ ~ , ,
; _
~ ~ - ~ _
~ . . ~ , . t . . . i
� ,
- . +1 . . I 1 I w 'Y . ~ ~1 . .
f : , af r y ~ _
~f ,
~ ' ' . ~ 3Z
� i y F . . .4. , ,
.
. "
.
. .
r . . . u . { ji ~
1.~..~... _ . . . . . ` . ~N� ~
_ ~
' ' . _ ' . . " . : - ~ '
Figure 8. Diagram of the GTRT~
From the presented data the exceptionally high complexity of buildi.ng the ~MS for
power reactors is clirectly obvious. The energy reserve in the SOTP of the GTRT
exceeds by two orders of magnitude the energy reserve of the SOTP of the T-15 and
the largest superconducting magnetic system in the world of the large BEBC hydrogen
chamber (W = 830 Mjoules). In addition, the operating conditions of the SOTP are _
harsher than for tYie annular windings of the bubble chambers not subjected to the
~ 44
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7 ~ ~
s '~~i ~i -
~r i
- Jr _ i
% ~
~ ~ !
3 \ ~h .
/ ?
/ ~
Z ~ ~
i ~
?
/ ~
� 3 4 S 6 7 8 9 IO
Figure 9. Poloidal field pattern of the GTRT.
Basic parameters of the GTRT electromagnetic system
Toroidal f ield in the center of the plasma cross
section, tesla 6 -
Maximum f ield of the SOTP, tesla 12
Energy reserve of the SOTP, gigajoules 70
Type of superconductor Nb3Sn -
Total current of the OI, Mamps 53
Total current of the OU, Mamps 19
Flux variation of the OI, W-sec 104(�52)
Energy reserve of the OI, gigajoules 1.2
Maximum induction in the core, tesla 5.7
f Maximum induction on the OI, tesla 3.7
Short term vari.ation rate of the field on the
- OI, tesla/sec 20-30 _
effects of variable fields and radiation. The creation of the SOU placed inside the
- SOTP and insurance of field variation rates in the SOI on the level of 2Q-30 tesla/
sec required at the beginning of the operating cycle to ignite the discharge and for
fast rise of the plasma current appeared to be ve�ry complicated. The creation of
pure reactors requires the construction of larger devices than the GTRT.
At the present tim~ the necessity for building devices that are intermediate be-
tween industrial reactors and the T-15 devices built at the present time in our
_ country and similar to it with respect to scales but not using superconductivity,
the foreign JET, TFTR and DZhT-60, is generally accepted. The basic purpose
of the devices is the solution of the physical and engineering problems and the
development of structural designs direc~tly connected with the structure of the
power reactors. For the soiution of this problem the IAE imeni I. V. Kurchatov and -
i~IIEFA imeni D. V. Yefremov Institutes began the development of a demonstration T-
20 thermonuclear reactor, and then the international reactor, the IIITOR tokamak.
Basic parameters of the INTQR
_ Large torus radius R~, m 5.2
Halfwidth of the plasma cross section a, m 1.3
Elongation of the plasma, v/a 1.6
DT-reaction combustion time, sec >100
Average ion density n,m 3 1.4�1020
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Average ion temperture Ti, kev 10
Plasma current Ipl, Mamps 6.4
Thermonuclear DT power P, megawatts 620 ~
Toroidal magnetic field at the center of the plasma '
_ crossection B0, tesla 5.5
Corrugation of the toroidal field on the edge of the
plasma, % +0.75
Neutron load on the first wall, Mwatts/m2 1.3
Reserve (number of operating cpcles) (0.5-1)�106 :
Neutral beam heating power, megawatts 75
Neutral beam energy, kev 175 ;
Fuel impregnation By gas, tablets
Impurity control Diverters
On the basis of the presented parameters, a preliminary calculation was performed, _
and thefollowing basic specif ications of the EMS were established:
Number of modules in the OTP 12 .
Maximum OTP induct3on, tesla 11.6
Energy reserve of the OTP magnetic f ield, ~
gigsjoules 40
Weight of the OTP module, tons 250
Total current of the OI, Mamps 125
Energy reserve of the OI, gigajoules 3.8
Total current of the OU, Mamps 30
Energy reserve of the OU, gigajoules 2�6
Average power of the OU, megawatts 50
Type of diverter Poloidal with 10
Weight of the EMS, tons 5000
Power of the cryogenic system on the level of -
4.5 K, kilowatts 50
Cool-down time 15 days
Structural Design of the EMS of the INTOR. Considering the experi~uental naturQ of ~
- the INTOR, the structural design of its EA*'IS must insure the possibility of eas}*
exchange of the models of the blanket elements and also a suff iciently simple method _
of replacing the individual parts of the chamber and the shielding in the intense -
_ radiation zone using robots. The requirement of replacement of sections of the
- chamber and shielding is determined both by the necessity for testing various ver-
sions of the structural elements and replacement and repair of them in case of dam-
age. Diverter plates are subject to regular replacement as a result of their
limited service life.
The structural diagram of one version of the EMS is presented in Figure 10. The
volwne of the EMS is broken down into f ive regions: a) high-vacuum discharge cham- -
ber; b) cryo~enic chamber containing the superconducting toroidal f ield winding -
(SOTP), induction coil (SOI) and control winding (SOU) are placed; c) the intermedi-
ate ''thermal" region with efficient shielding by the blanket modules and "thermal"
resistive control windings (ROU) located in it; d) central near-axial region with _
resistive induction coil (ROI) in it; e) diverter region. _
Regions a, b, c are separated from each other and from the outside space by vacuum-
tight walls, and they have separate vacuum exhaust. The evacuation of the cryogenic
46
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region is necessary to insurP thermal insulation of the superconducting windings. '
The evacuation of the intermediate region facilitates protection in the case of
tritium leaks. Between the SOTP coils around the peri.meter of the EMS provision
is made far the "corridors" joining the intermediate region to the outside space
permitting the installation modules into which the chamber and the shielding are
broken down to be shifted along the radius. Thus, any part of the chamber and the
protection can be replaced without heating the superconducting windings.
As a result of complexity of repair, i.n particular, after radiation contamination
~ of the devic~, the windings of the electromagnetic system must be made with a margin
of reliability such as to reduce the probability of failure during the operating
time of the INTOR to a minimum. It appears that this problem can be solved.
Superconducting Toroidal Field Winding of the INTOR. Maximum induction of the toroi-
dal magnetic field exceeds 11 tssla. For suchinduction, si.gnificant ponderomotive
_ forces acting on the winding and variable poloidal magnetic fields,there is a high
probability of the appearance of thermal disturbances capable of converting the
sections of the SOTP to the normal state. Accordingly, the toroidal f ield winding
must have sufficient reserve with respect to critical current and temperature and -
a high degree of stabilization such that the short-term disturbances causing the -
appearance of sections of the normal phase will not lead to transition of the entire
winding to the normal state. The indicated requirements can be satisf ied by the '
superconducting conductor (SP) based on Nb Sn. It is known that the current-carry-
ing capacity of the composite, thin�-strand3superconductors based on Nb Sn in prac-
t ice is not ~educed for def ormations of E< 0.5% and neutron f luxes to3on the order
of 1018 N/cm . The industrial manufacturing process for such Si' has been developed,
and their cost will be reduced with an increase in the scale of the industrial
output. It is possible to calculate that the experience in building LCP and the T-
_ 15 windings will confirm the expediency of using Nb3Sn f or INTOR and power engineer-
ing reactors. For the SOTP on the INTOR, it is expedient to use copper as the _
stabilizing metal. The application of aluminum, in spite of the fact that there is
less of a shortage of it, lower cost and less magnetic resistance, is li~ited by the
low mechanical strength and high variation of the resistance in the presence of
radiation. In addition, in practice there is no experience in the manufacture,
operation and maintenance of Nb3Sn superconductors stabilized by aluminum. However,
i~ is necessary to continue the operations of investigating the possibility of
creating aluminum-stabilized superconductors from Nb3Sn for tokamaks.
For the SOTP, a circulating cooling system is proposed which has define~ advantages
by comparison with the submersible one: during circulation cooling, the structural
- design of the cryostat is simplif ied, the problems of insuring electric and mechani-
cal strength are solved more simply.
_ Both the single-phase and dual-phase helium can be used for cooling. At the present
time it is diff icult to give preference to any of these versions. The e~erimental
study of both versions is proposed, in particular, on the T-15 device.
In the investigated version it is proposed that the SOTP be made of 12 coils of the
modified D-ty;~e. The quantity and the dimensions of the coils are selected in such
_ , a way that tole:rances on the corrugation of the toroidal field will be satisf ied,
the possibility of input of the neutrals to the discharge chamber and rolling out
the chamber and shielding modules thr~ugh the "corridors" in the gap between the
~OTP coils will be insured. -
47
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The mass of the toroidal coil of 250 tons will not lead to extraordinary installa- '
tion diff iculties.
The poloidal magnetic field winding system includes inductor winding, the plasma. _
equilibrium and shape control winding and corxecting windings (OK). For arguments
of economizing on energy losses, these windinge are expediently mac?e superconduct~
ing. However, this solution is complicated by the necessity f or creating quite
rapidly varyi.ng f ields from them defined by the operating pulse parameters.
By the conditions of the physics of plasma formation at the beginning of the opera- -
ting cycle for ionization of the DT gas in the discharge chamber and rise of the
_ g~asma current to approximately 0.1 Mamps, it is necessary briefly to generate an
emf of 100 volts on the bypass of the discharge chambe.r and then reduce it to 25
volts and less in order to realize further buildup of the plasma current. This
requires high speed of field variation (B ~ 20 tesla/sec.) in the SOI region at the
start of discharge, which can lead to transition of the SOI to the normal state.
6
6 ~
~
9M
a ~ ~
- . . ~ ti
I~
,2
I
~a~co.r~ (b) PON caa cvr~
76,.~ (c)_ (d)
Figure 10. Structural diagram of the INTOR
eletromagnetic system.
Key: a. SOU c. SOI
b. ROI d. SOTP
The ap~lication of an additional resistive inductor winding installed inside the
SOI permits insurance of high volta;e at the plasma bypass in the initial discharge
stage, at the same ti.me l~iting th~. variation �rate of the f ield in the SOI super-
conductor on an acceptable level. The resistive winding of the induction coil must
_ have approximately the same number of turns as the superconducting winding, and it
is connected parallel to it. -
- Before tne beginning of discharge, the remagnetization current is initially induced `
in the SOI, and then in the ROI after connection of it parallel to the SOI. After
_ response of the breaker, for leadout of the energy from the OI first the current and
the magnetic field of the resistive winding decrease quickly, and the current in the
, magnetic field in the turns of the superconducting winding remain in practice un- _
changed as a result of mutual ~:ompensation of the emf and voltage applied to the
SOI turns. When the voltage on the inductor turns decreases to 25 volts/turn, and
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the current in the ROI drops to zero, the ROI is disconnected, and further varia-
tion of the emf will be crea.ted by the 501~. Thus, the ROI insures fast variation
~ of the inductor f 1~ at :.he start of discharge, and the SOI insures slow variation
of the inductor flux during the entire discharge. Along with reducing the varia-
tion rate of the field in the vicinity of the SOI, the application of the ROI per- _
mits the maximum induction and the amount of SOI superconductor to be decreased.
Maintenance of the plasma equilibrium in the required staape of its transverse cross-
section and formation of the diverter field are realized using the OU. The same
windings generate part of the eddy emf required to insure current buildup of the
- plasma. The magnetic f ield calculations demonstrated that for placement of the OU
- inside the SOTP the total current, the OU energy reserve and the tipping moment
decrease by several ti.mes. The variation rates of the fields in the vicinity of the
- OTP conductors are reduced significantly.
However, the creation of reliable superconducting control windings located inside
the SOTP appears to be a~~ery real problem. Obviously, sufficiently reliable EMS
with OU inside the SOTP can be constructed only when using ordinary copper resistive
conductors for the OU; however, there will be significantly active energy losses -
- here.
- BIBLIOGRAPHY
l. D. P. Ivanov, V. Ye. Keylin, B~ A. Stavisskiy, N. A. Chernoplekov, "Supercon-
ducting Toroidal Solenoid for the'Tokamak-7'," ATOMNAYA ENERGIYA (Atomic Power),
' Vol 45, 1978, p 171.
2. V. A. Glukhikh, L. B. Dinaburg, N. I. Doynikov, et al., "Engineering Problems of
Rebuilding the 'Tokamak-10' Device," DOKLADY VSESOYUZNOY KONFERENTSII PO INZHENER-
. NYM PROBLEMAM TERMOYADERNYKH REAKTOROV (Reports of the All-Union Conference on
, Engineering Problems of Thermonuclear Reactors), Leningrad, NIIEFA, Vol 1, pp
26-41.
3. V. Ye. I:eylin, Ye. Yu. Klimenko, I. A. Kovalev, et a].., "Stabilized, High-Current
Niobium-Tin Solenoid," DOKLADY VSESOYUZNOY KONFERENTSTI PO INZHENERNYM Pi~OBLEMAi~
TERMOYADERNYKH REAKTOROV, Leningrad, NIIEFA, Vol 1, 1977, pp 179-187.
4. E. N. Bondarchulc, I~. I. Doynikov, A. I. K~stenko, et al, "Effect of Plasma Cur-
rent Cutoffs on the Operating Stability of a Superconducting Toroidal Magnetic
Field Winding of the T-lOM Device," Preprint P-B-0416, Leningrad, NIIEFA, 1979. -
S. Ye. P. Velikho v, V. A. Glukhikh, V. V. Gur'yev, et al., "Hybrid Thermonuclear
Reactor of a Tokamak for Producing Fissionable Fuel and Electric Power," DOKLADY
VSESOYUZIIOY KONFERENTSII PO INZHENERNYM PROBLEMAM TERMOYADERNYKti REAKTOROV, ~
Leningrad, iVIIEFA, Vol 1, 1977, pp 5-25.
COPYRIGHT: Energoizdat, "Elektrotekhnika", 1981
[161-10845]
10845
- CSO: 1860
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,
UDC 621.311~6:621.039.6
POWER SUPPLY SYSTEM FOR THE TOKAMAIC 7.'3(PE THERMONUCLEAR DEVICES
Moscow ELEKTROTEKHNIiCA in Russian No 1, Jan 81 pp 16-2Q
[Article by Ye. V. Kornakov, engineer, F. M. Spevakova, candidate of technical
sciences, A. M. SColov, doctor of technical s:.iences]
[Text] One of the most i.mportant problems occurring when building the tokamak type
devices is creation of power supplies for the electromagnetic system characterized
by very high powers and stored energies. The complex tokama.k power supply system
consists of a number of devices designed to create a toroidal stabilizing field and _
poloidal field insuring the occurrence of a plasma column, resistance heating of the _
plasma and also maintaining equilibrium of the plasma co'lumn. Each of these power
supplies is a device that provides for generation of pulses of a defined sha.pe and -

- characterized by different powers and required energies.
Toroidal Field Winding Feed Systems. The toroidal f ield winding~ require power
supplies with energy reserves much higher than the other windings of the electromag-
= netic system. In the,operatin~, part of the pulse (the plasma heating period), tne _
toroidal field must be kept constant. The energy required of the power supply is
defined both by the winding parameters and the duration of the work:+.ng part of the
pulse which can vary within broad limits.
The basic parameters of the toroidal field power supply systems of toka~naks de-
veloped at the NIIEFp. imeni D. V. Yefremov Institute are presented ~.n the Y.able. _
The required energy r.eserve of the toroidal f ield power supply determines the choice
of the technical sc,lution.
For devices with comparatively small intake powers (to several megajoules), the
pulsed sources with capacitor banks are the most widespread (see Figure 1). The
current rise in the toroidal field winding L takes place using a previously charged =
converter II of the capacitor bank C on inclusion of the commutator K. When the
capacitor bank discharges, and its voltage begins to change polarity, the diode D "
that shunts the winding is included. Then the winding current decreases by an
exponential law, and the commutator K disconnects the capacitor bank. In the case
where the time constant of the winding essentially exceeds the duration of tne
operating part of the pulse, the toroidal field in this interval is in practice -
constant. This system, distinguished by comparative simplicity and reliability,
wa.s used on the Tri-4A device.
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With an increase in the intake power to values exceeding 10 Mjoules, it appears to
_ be more expedient to use valve converters as the power supplies. Here the ratio of
- the total power released in the winding w~ to the energy released in the winding
during the operating part of the pulse w 1 is defined by t~e ratio of the time con-
stant of the winding T to the duration o~ the working part of the pulse tQ and the
forcing coefficient k, thaC is,
' T k 1 2
_ w~ I-I- to k' ~ln k-1 k,.
(a)
Key: a, wDl
Name of device Plasma confine- Energy reserve Maximum power
ment time, sec in the toroidal of the power
f ield winding, supply, Mwatts -
M'oules
TM-4A tokamak 0.015 5 500.00
T-3 tokamak 0.050 60 77.00
- T-10 tokamak 1.000 400 160.00
T-15 tokamak * 5.000 750 0.45
_ *
In the construction phase.
By the f orcing coeff icient k we mean the ratio of the converter power during rise of
the winding current to the power in the working part of the pu?se. With an increa~P
in the forcing coeff icient, the total energy consumption dec~ ases, but the conver-
ter power increases. Usually the forcing coefficient is define:' by t-' P admissible ~
magnitude of the thermal losses released in the winding of the toroi~a:L field. In
the power supply systems with converters, the winding current builds up with maxi-
mum voltage of the converters; the current area is shaped with raduced voltage, and
the current drop is realized in the inverter mode.
~
Depending on the possibilities of the electric power supply system of a the.rmonuc-
lear device, the converters can be fed directly from the network or from the elec- _
tric motor units with f lywheels i.f the fee~ network does not permit power surges.
For example, the toroidal tield of the T-3 tokamak was created using ignitron con-
verters fed by a synchronous generator with peak power of 77 Mwatts (Figure 2).
The maximum winding current L was 7000 amps; the no-load rectified voltage of the _
ignitron converters IP was 11 kv. The drive of the unit was from an asynchronous
motor D with slip regulator PC. During the shaping of the pulse the sli:p of the -
unit varied from 1 to 18%. -
On the T-10 tokamak, in connection with increased power of the feed network, it �
tu~ned out to be possible to directly feed the converters through anode transformers
- from the network. ~
-M. A. Gashev, et al., "Basic Technical Specifications of an Experi.mental 'iokamak-
3` Thermonuclear Device," ATOMtdAYA ENERGIYA (Nuclear Power), No 4, 1964.
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The converters developed and manufactured by the KhEMZ plant with maximum current
of 20 kiloamps and total no-load voltage of 8 kv were made from thyristors~ llne of
the problems arising when building systems with converters is the choice of the ~
- method of adding their powers. The most expedient appears to be the use of a 12-
_ pulse system of the converter unit. This system is formed by tw~ thr~e-phase b~idge ;
circuits joined in parallel or in series.
- With parallel connection of the converter units, the currents under emergency condi- _
tions increase . With series connection of the converters, the winding voltage of
the converters relative to the ground increases. Some of the methods of lowering
the winding voltage with respect to ground are breaking it down into sections and
series-alternate inclusion of the sections of the winding and the converters. In
this case the winding voltage with respect to ground can be reduced a number of
times equal to the number of sections. Figure 3 shows the power system for the
toroidal field winding of the T-10 tokamak. The winding consists of four sections
L1-L4. In this system with nonsimultaneous opening of the converters lIl-1I8, the
winding potentials with respect to ground increase, for the elimination of which a
special high-speed protection is required.
During operation of the converters with signiticant forcing coeff icients, the de-
crease in winding voltage in the operating part of the pulse as a result of an in-
- crease in the angle of regulation of the converters leads to significant growth of
he reactive power intake from the network. -
K
~ n c p a
Figure 1. Power supply for the TM-4 tokamak
toroidal f ield winding.
, w.~ .
O ~ er
, ~
rG �
en en ~
K �
R R ?
1
- Figure 2. Power supply of the toroidal field
winding of the T-3 tokamak. I' generator; -
M-- flywheel; BI' auxiliary generator.
In the system with series-alternate connection of the converters and winding sec-
tions, the possibility arises for decreasing the winding voltage by excluding part
of the converters from the circuit with the help of commutation equipment. As an
example Figure 4 shows a diagram of the series-alternate connection of two conver-
ters and two sections of a winding. For exclusion of the converter lIl from the
circuit, the latter is converted to the inverter mode, it is shunted by the commu-
' tator K, and after deexcitation, disconnected by the P1 and P2 disconnects. The
disconnected converter can 'oe used to power other windings of the thermonuclear
device in the operating part of the cycle.
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T1 72 TJ T4
~ ~
- m ~ nz /IJ /!4 /!5 /!6 /17 ne
L1 L2 L3 L4
- ~ R1 RZ _ R3 _ R4
Figure 3. Power supply of the toroidal field winding of
the T-10 tokamak. Tl~-T4 anode transformer; Rl-R4
_ ground resistors.
A.deerease in the reactive power intake from the network, when it is necessary to in-
crease the angle of adjustment of the converters, can be achieved by application of
an asymmetric control circuit. If in the two series-connected bridge circuits fed
by cophasal voltage, the ignition angle of the catho3e group of the f irst bridge and
the anode group of the second bridge is increased simultaneously by the same amount,
� the resultant voltage will be six-pulse, and the reactive power intake from the
network, with an increase in the adjustment angle by more than 30%, begins to de-
crease by comparison with the circuit with symnetric control, and thi:s decrease� is
, greater, the greater the angle of adjustment. In the system with a multiple of four
converters, with asymmetric control circuit, the 12-pulse converter can be main-
tained, With parallel connection of the power supply converters, an asymmetric
control can also be used, but in this case it is necessary to connect the two bridges
fed by the cophasal voltages, in c~ne of which the cathode group of valves is adjusted
and the other, the anode group, in parallel through a disconnect reactor. For
_ creation of a 12-pulse circuit with parallel connection of the converters it is also
~ necessary to have a multiple of four valve groups. Three separating reactors are
required in th ~is case .
In cases where the power required to shape the pulses in the toroidal f ield winding
reaches such large amounts that the direct feed from the network or from the elec-
trode of inechanical units with flywheels is connected with engineering problems that
- are diff icult to resolve and with high cost of equipment, the circuits with the
application of inductive storage elements with an energy reserve that is no less than -
four times the reserve of the electromagnetic energy of the load turn out to be more
expedien t. As the source of charge of the storage elaments, homopolar generators -
or valve converters can be used.
pr a�
I M nt~~l
rt cr
Figure 4. Diagram of the power supply with a
decrease in the reactive power consumption.
When building feed systems with inductive storage elements~ one of the basic prob-
lems is the creation of the high-power commutation equipment (disconnectis). In d
number of cases, for matching the parameters of the feed systems, the commutation
equipment and the requi;cements advanced by the effort to realize optimal structural -
design of the device, it is expedient to use two winding inductive storage elements.
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~
L1 P~ LZ py LJ Ln p~ !
Rt J R4 S B6 /P(Zn ;
~ ~(Z/~ -1) i
T
Figure 5. Diagram of the power supply of a -
superconducting winding. L1-Ln winding
sections; II-- feed converter; Pl-Pn
disconnects. .
In order to reduce the voltage on the inductive storage element and the toroidal -
field winding f ed by it with respect to ground, both the storage e.lement and the '
winding can be made sectional with series-alternate inclusion of the storage ele- .
ment sections and the winding.
A significant reduction in power of the power supplies of toroidal field windings ~
_ can be achieved on application of a supercondu~ting magnetic system. In this case
a constant toroidal field is created, and the poloidal f ield and correction windings
operate in the cyclic mode. Since the energy accumulation in a superconducting ;
winding can take place over a prolonged time period, the power of the converter
feeding the winding can be comparatively small. For example, in a toroidal field
- winding of the T-15 tok.amak built at the present time, the current buildup takes
_ place in two hours.
Wh~n creating the feed system of a superconducting winding, one of the serious
- problems is inaurance of fast energy output from the winding on the occurxence of a
normal phase of the conductor. A fast drop in the current can be achieved on intro-
duction of an active resistance into the winding circuit. Here, the smaller the -
time constant of the c~rcuit on output of the energy, the higher the voltage occur- ~
ring on the winding. In order to reduce the winding voltage with respect to ground ;
it is expedient to section the winding and insure energy output by the introduction
of active resistances between the sections of the windings as a result of response '
of the breakers shunting the resistances.
One of the possible~versions of such a system is illustrated in Figure 5. However,
in this system, on inducing a current in the winding, imbalance occurs between the
- currents of the individual sections. The magnitude of this imbalance turns out to
be comparatively small, for the excitation of the superconducting.winding takes
place for a voltage of quite small magnitudE. After completion of i.nduction of the
current and a decrease in the voltage to zero in the sections, the imbalance de-~:
creases and reaches zero. The system in Figure S with execution of a winding from
- four sections was used to feed the toroidal f ield winding of the T-15 tokamak.
- Obviously, hereafter when building sufficiently large-scale devices of the tokamak
; type, the spplication of the superconducting toroidal f ield windings will be the -
most expedient technical solution.
Feed Systems of Poloidal Field Windings. As is known, the creation of the plasma
current in the tokamak type devices is insured by the induction method using ir~e
winding called an inductor. As a result of the peculiarities of the structural de-
signs of the tokamaks, the inductor is located at comparatively large distances
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from tb.e plasma column, the coefficient of magnetic coupling of the inductor to the
plasma column is comparatively small, and the pulse power required from the Power
supply is determined to a significant degree by the reserves of electromagnetic
energy and also the active losses in the plasma. The poloidal field is f ormed both -
= by the inductor winding and the control windings designed to insure the condition of
equilibrium of the plasma turn. The number of control windings is determined by the
specif ic structural design of the electromagnetic system.
In spite of the fact that the feed system of the inductor cannot be considered in-
sulated, without connecting the power supplies for the control windings, in a num-
ber ot case~ it is possible to create independent feed systems.
. The inductor feed systems can be based on different principles: using the inductor
of the primary winding of the transformer, the secondary winding of which is a plasma
coil, and with the application of an inductoY as an inciuctive"energy storage element.
In each of these versions, in order to increase the range of variation of the induc-
tive flux it is expedient to use demagnetization of the core, which when using an -
inductor as a storage element permits simultaneous decrease in power of the feed
_ equipment and the commutation unit.
The shape of tiie plaswa current puise can be close to trapezoidal with a duration
of the plane peak exceeding the rise and faYl time of *he current. A characteris-
tic feature of the operation of the inductor power supplies is nonlinear nature of
- the load. The conductivity of the plasma varies by several orders, and the self-
induction coefficient of the plasma coil also varies during heating and variation
in size of cross section of the plasma column.
A r_omparatively large pulse power is required of the power supplies for fas~ ris~: of
the plasma current, and appreciably less, for maintaining constancy of the plasma
coil current. In systems with comparatively small energy reserves required to
~ generate the ~lasms current pulses, artificial lines can be used as the power
supplies. In order to decreas~ the effect of the variation of the load parameters
on the processes in the official line, a ballast resistor is included in series -
with the inductor winding. This system was used to feed the TM-4A takamak iflductor ~
_ for shaping the plasma current pulse with front and decline duration of two milli-
- seconds and an area of 15 milliseconds. The current amplitude of the inductor
winding was 9000 amps, the energy reserve in the capacitors of the artificial line,
0.4 Mjoules.
For a duration of the shaped pulse on the order of tens of millis~^onds and required -
energy reserve of the inductor winding on the order of several megaj~ules, a feed
system with capacitance pulse that is variable in time (see Figure 6~ can be used
as one possible version. The initial rise of the load current takes ~:lace as a re-
sult of discharge of the capacitor bank C1. Then the commutation of. the capacitor
banks charged to different voltages is realized by means of diodes. In this system
the capacitance of the circuit varies automatically. This system was used on the
- T-3 device witl~ four groups of capacitor banks with total energy reserve of 2M-
joule~.l
lIb id .
- 55
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In cases where the durati.on of the plasma current pulse exceeds tens of millisec-
ands, and significant energies of the power supplies are required, it is expedient
to use combined circuits in which the rise in current is realized by a high voltage
source, and maintenance of constancy of the current at the peak, by a lo~.~ voltage
source included in series with the high voltage source. This system was used in
. the power supply for the inductor of the T-10 device (see rigure 7). A two-stage
capacitor bank with total energy reserve of S Mjoules was used as the high-voltage
source, and the lt2 thyristor converter with a power of 40 megawatts, as the low-
voltage source. In order to eliminate overvoltages on the anode transformer AT, ~
which can occur at the beginning of discharge of the bank for defined ratios of the
load inductance and the scattering inductance of the anode transformer, the conver-
ter li2 is shunted by the diode D1. The same result can be achieved for simultan~ous
ignition of two opposite arms of the bridge II2 and absence of the control pulses on
the other valves of the converter in the time interval from the beginning of the -
discharge of the capacitor bank to the time the bank reaches a voltage equal to the
vo~tage of the converter II2. As the high voltage source providing for f ast rise of _
_ the plasma current, an inductive energy storage element can be used. The inductive
storage element previously charged with the help of a converter transmits part of
the stored energy to the inductor on response of the breaker that shunts the
resistor R. Af ter the current rises to the given value the resistor is shunted by F
a switch, and the inductor current is maintained by using a second converter.
In the investigated inductar winding feed systems, the induction coil was used as
the primary winding of the transformer. With an increase in the inductor energy
reserve and the required power, the systems using an inductor as an inductive stor-
age element turned out to be more expedient. In such systems the power intake for
initiation and the beginning of the rise of the plasma current was provided f or by
the inductor itself with release of the energy stored in it during the core demag-
netization process. A further rise in the plasma curient and maintenance of its
given value can be insured by the converter. The p~wer supply system based on these
principles (see Figure 8) was used to power the T-15 tokamak inductor.
The demagnetization of the core is realized by the converter II with the commutators
K1, K3 included. On completion of demagnetization, the converter II is converted -
to the inverter mode and the disconnect P responds simultaneous~y, introducing the
resistor R into the circuit. A voltage will come up in the inductor winding in
this case tha.t will provide for breakdown in the discharge chamber and fast buildup
of the plasma current. The inductor current decreases, and when it reaches zero,
the switch 3 closes, the commutators K1, K3 open, and the commutators K2, K4 close.
The inductor current begins to bui.ld up in the opposite direction, and the required
law of variation of the inductor current is provided by the converter II. In the
T-15 tokamak inductor f eed system, an 80,000 amp, 1000 volt thyristor converter is
used. The breaker provides a voltage of 8000 volts in the inductor.
K
tI~ d: q?
- t~ GI =c ~
_J
- Figure 6. Circuit diagram with variable
- capacitance (Li inductor winding).
56
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R
~r
c
~ n~ -rc qr
nz A?
Figure 7. Power supply of the inductor with
capacitor bank and dc power supply. -
P
R
XI A'4 J .
n ~u
R2 NJ .
= Figure 8. Inductor power system with mechanical
reverser (K1-K4 mEChanical reverser commutators).
In connection with the development of the tokamak type devices, improvement of their
parameters and an effort to achieve higher plasma parameters, the f unctions of the
power supply systems have become more complicated. Whereas in the initial phase of
= development of the tokamaks on the T-3 device the polaidal f ield was determined by
the inductor winding and eurrents induced in the massive housing, hereafter on the
TM-4A and T-10 devices, it was necessary to install an additional control winding _
_ each to insure plasma equilibrium. The power supply system of the control winding
~ of the T-10 tokamak provided for the cr~eation of a pulse of special shape and was
a 10 Mwatt thyristor converter which st:aped the pulse as a result of variation of
the adjustment angle using a programmed regulator.
In the developments of the devices of the next generation it was necessary to in-
sure the exact equilibrium conditions of the plasma coil taking :(nto account the
_ ratio of the control f ield and the plasma current and also the influence of the gas
dynamic pressure of the plasma column on the equilibrium condition. Therefore it
turned out to be expedient to build inductor and control winding power supply sys-
~ tems by a united principle. For example, on the TM-4A device, both the inductor
winding and the control winding are powered by identical devices artificial lines.
- On the T-15 tokamak the control field is created by three windings, each of the power
supply systems of which, just as *he feed system of the inductor winding is a combi-
nation of a high voltage source and controlled thyristor converter for comparatively
low voltage. In order to improvP the equilibrium conditions of the plasma, these
converters operate by the program corrected from pulse to pulse using regulators -
in the plasma column position function.
Further improvement of the cc~nditions of equilibrium of the plasma is achieved by
using, in addition to the control windings, auxiliary systems that provide for
high-speed adjustment of the position of the plasma colwnn using f eedback. One of
the versions of such a system is the device based on the principle of pulse-width
regulation which it is proposed will be used on the T-15 device.
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As was demonstrated, with the development of experimental th~rmonuclear devices, the
energies and powers of the feed system ir?creased and the f unctions of such systems
also became more complicated. Since in the near future the transition from experi- .
mental to power engineering thermonuclear devices is expected, the requirements on
the power supply systems will be altered. In addition to the necessity for creating
devices characterized by energies on the order o~ megajoules and powers on the order
of many hundreds of magawatts, feed systems with high operating reliability and high
_ pff iciency are required which are economical, completely automated with long opera- _
ting reserve of each assembly and simple to maintain.
COPYRIGHT: Energoizdat, "Elektrotekhnika", 1981
~i6i-iosa5]
10845
CSO: 1860
_
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UDC 621.311.6.025
POWERFUL AC UNITS WITH INLRTIAL ENERGY STORAGE ELEMENTS FOR FEEDING ELECTROPHYSICAL
DEVIC~S
. Moscow ~LEKTROTEKHNIKA in Russian No 1, .Tan t31 pp 20-22
[Article by I. A. Glebov, academician of tre USSR Academy of Sciences, E. G. Kashar-
skiy, doctor of technical sciences, F. G. Rutberg, candidate of technical sciences,
G. M. Khutoretskiy, doctor of technical sciences]
[Text] Autonomous power ~ugplies are being used to feed some of the electrophysical
, loads having a short-term nature. If the r~guired power levels are in the range of
108 to 109 watts with an energy of 10$ to 101~ joules, the electromechanical unit
operating with variable rpm is the preferred power supply. In this case, the
- energy of rotating masses is used. This energy is converted to the energy of a mag-
netic f ield or arc discharge on deceleration.
The electromechanical unit usually consists of a generator, flywhee~~, and drive motor.
In addition, aux.iliary machines the contiol system sensors can be put on the
shaft. Both turbogenerators and salient-pole synchronous motors are used for the -
short-term electromechanical units. The latter can be in both the horizontal and -
vertical positions. The role of the flywheel can be perf ormed by a weighted gene-
rator rotor.
Such a storage unit has three characteristic operating conditions corresponding to
the storage of power (acceleration), conservation of energy in an inertial storage
element (idle without excitation or with excitation) and energy release (braking).
At the present time in Soviet practice def inite experience has been accumulated in
the use of standard synchronous generators in the braking mode on an active load.
There is also foreign and Soviet experience in the design of ,pecial units for feed- -
ing electrophysical loads [1, 2, 5].
The purpose of this paper is to analyze the basic character istics connected with the :
design and the ~perating conditions of such units.
The data on the largest units are presented in the table. Units with inertial
storage elements are accelerated, as a rule, as a result of the app~.ication of
asynchronous motors with phase rotor. In some devices with rpm close to synchronous,
a thyristor frequency converter is connected to the circuit of tY?e rotor windtng of
the motor, which permits smoother regulation of the rpm and also raising of it above
synchronous. The anplication of the frequency starting method also appears to be
prospective.
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The primary problem which is solved whe.n designing an energy storage element with a
f lywheel is insurance of the required level of st:orage power.
In the structural execution of the flywheels it is possible to iso~ate several
basic areas (see Figure 1). The most important cr iterion for estimating the struc- '
- tural design of a f lywheel is the specific energy capacity the ratio of the !
energy accumulated in it to its ~ass. The maximum achieved value of the specif ic
energy capacity for isotrdpic titanium flywheels is approximately 10~ joules/g; for
steel flywheels it is approximately 60 joules/g, and for flywheels made of beryllium
bronze, about 65 joules/g. However, for the isotropic f lywheel with high specif ic
energy capacity with respect to Figure l,a, b ther e is a restriction on its energy
capacity as a whole. The transverse (axial) size of such flywheels must not exceed
200--300 mm, which makes it possible to forge the f lywheel from the lateral surfaces
and also to realize effective ultrasonic and physical monitoring of the presence of
microcracks and disturbances of the internal structure. Increased values of the
admissible stresses are established by the strength conditions, respectively.
The diameter of ;:he forging, in addition to the strength conditions, is also limited
by the possibilities of the process equipment. Therefore for isotropic flywheels, .
according to Figure 1, a, b the stored energy is limited in the f uture to a value on
the order to 108 joules for sCeel flywheels and 2�10$ joules for titanium alloy
flywheels. -
A further increase in the amount of stored energy can be realized as a result of
increasing the length with transition to cylindrical sha.pe of the flywheel. ilere _
the f orging conditions are improved, the admissib le stresses are decreased and,
consequently the specif ic energy consumption is reduced. The modern technology for
obtaining large cylindrical flyw'~eels is based on the experience in manufacturing
all-forged rotors for large turbogenerators. The specif ic energy capacity of such _
f lywheels is 10-18 joules/g~ According to [3] it is possible to assume tha.t the
manuf acture of an all-forged stesl cy~.indrical f lywheel weighing about 300 tor~s is
realistic. Such a flywheel obviously could store energy on the order of 4�10 -
joules.
Another area of manufacture of heavy flywheels is assembled rotors. Thus, the mag-
nitude of the specific energy consumption of the flywheel built by the "Siemens"
Company is 16 joules/g with a stored energy of 3.5�10g j oules. The growth in the
diameter of the assembled flywheels is also limited by strength conditions, and
increasing the length is limited by th~ vibration resistance requirements.
Further increase in the amount of stored energy is possible by installing units with
two or more flywheels each [2]. ~
In the future nonmetallic composites formed by glass, quartz or similar f iber will
have definite advantages for flywheel manufactur e Such materials have a high ratio
of admissible voltage to specific weight (to 5�10~ cm and higher). According to .
[4], in the near future the technical possibilities will permit the manufacture of
flywheels with a specif ic energy capacity of 240-314 joules/g with an energy capa-
city of one flywheel to 0.7�109 joules. However, it is necessary to note that at
the present time the ma.nufacturing technology f or large-scale f lywheels made ~f
nonmetallic materials has been insuff iciently d eveloped. -
60 -
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" ~ _ -
~
c)
~ a~ ~b )
_
i
d) e)
Figure l. Structural forms of flywheels used for storage units.
a-- equal-strength; b-- conical; c-- cylindrical all-forged;
d-~- cylindrical compositional; e-- with vertical shaft.
Another method of improving the general energy capacity of the unit is the transi-
tion to a structural design with vertical shaft. In this case the salient-pole ~
- generator approaches the hydrogenerator with respect to type. It is most expedient
to match the flywheel to the generator rotor. The specif ic energy.capacity of this
rotor-flywheel does not exceed 1-S joules/g, but on the basis of the increased
load capacity of the thrust bearings by comparison with other bearings, and also as
a result of the absence of vibrational restrictions in the future a total energy
capacity on the order of 1010 joules and even higher can be reached here.
The most typical for the units with inertial storage elements are the feed condi- -
tions of either the magnet through the rectif ier o:. the electric arc load. These _
operating conditions have been described in suff:Lcient detail in [1]. Their basic _
difference consists in the f act that with arc loading i~ is desirable to output
power as uniformly as possible, and on charging of the electromagnetic storage ele-
- ment (magnet) the largest current is reached at the end of the regime ~an rhere is a
noticeable reduction in the rpm. This part of the regime is the harshest with re-
spect to electromagnetic and thermal loads both with electric arc discharge and
especially in the inductive storage element charging mode. At the same time the
initial part of the braking mode when feeding the magnet is characterized by poor
use of the generator with respect to power, inasmuch as tY?e stator current increases _
on charging from 0 to the maximum value permitted by the thermal and thermomechani-
cal restrictions. The choice of the law of regulation of the excitation during the
process of braking of the unit has.great significance. When feeding an active load,
it is usually desir able to have the voltage invariant. Inasmuch as, as a result
of the reduction in frequency during braking the generator emf decreases propor-
_ tionally, the voltage level maintained using the excitation regulator must be taken
as somewhaC lower than rated (Figuxe 2, curves 1 and 2). The line 1 corresponds to
more complete use of the energy capabilities of the flywheel. The saturation level
with respect to the magnetic flux at the points of completion of the regime lies
within the limits of 1.1-1.2, and in some cases, even higher.
, When feeding the inductive storage element through the rectifier, it is eff icient
before the beginning of the regime to assume that the voltage is rated or even
higher than rated by 5-10%. During the course of the f eed regime, proportional re-
duction in the voltage can be permitted (Figure 2, curve 3). However, from the
~ ~ 61
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