JPRS ID: 10453 USSR REPORT ENGINEERING AND EQUIPMENT

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• Collection: JPRS
• Document Number (FOIA) /ESDN (CREST): CIA-RDP82-00850R000500050029-0
• Release Decision: RIF
• Original Classification: U
• Document Page Count: 51
• Document Creation Date: November 1, 2016
• Sequence Number: 29
• Content Type: REPORTS

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~ JPRS L/ 10453
13 April 1982~
- U~~R Re ort
p
ENGINEERING AND EQIJIPId~ENT
- CFOUC~ 3/82)
= F~IS FOREIGN BROADCAST INFORMATION SERVICE
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= NOTE
~ JPRS publications contain information primarily from foreign
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JPRS L/10453
13 April 1982
USSR REPORT
ENGINEERING AND EGIUIPMENT
~ (,'~'OUO 3/8 2 )
CONTENTS
NUCLEAR ENERGY
.
Improving Reliability and Economic Efficiency of Thermal ~
and Nuclear Power Planta 1
- Construction of Nuclear and Organic-Fuel-Fired Power Plants $
Research and Development of Materials for Nuclear Fueion
Reactors 10
TURBINE AIJD ENGINE DESIGN
Turbodynamos 24
- NAVIGATION .AND GUIDANCE SYSTEMS
Man as El~ment of Follow-Up System 31
- FLUID MECHANICS ~
Influence of Small Amounts of Poly:aer Additives Introduced ~
Into Stream on Hydrodyna~Tic Characteristics of Flat ~
Airfoils 35
Thermodynamics, Heat-and-Mass Transfer in Low-Temperature
- APParatua 44
~ - a - [TI~ - .USSR - 2].F S&T FOUO]
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NUCZEAR ENERGY
�
�
TMPROVING ~'ELIABZI.ITy [~Tp ECOPlOMIC EFFICIrPICY OF THFRMAL AND NUCLEAR POi~IER
PLANTS
~ Moscow TRUDY MOSKOVSKOGO.ORDENA LENTNA T ORDEN~, OKTYABR'SKOY REVOLUTSIT ENERGETI-
~ CHESKOGO INSTITUTA, TEMATICHESKIY SBORNTK: POVYSHENTYE NADEZHNOSTI I EKONOMICH-
, NOSTI TES I AES in Russian No 503, 1980 (signed to press 10 Feb 81) pp 2, 173-179
~ [Annotation and abstracts from collection of papers "Improving the Reliability and
~ Economic Eff3ciency of Thermal and Nuclear Power Plants", edited by Doctor of
Technical Sciences Professor N.G. :assokhin, Moscow Power Engineer3.ng Tnstitute,
~ 500 copies, 179 pages]
[Text] In this collection are presented articles by associates of the departments
of nuclear electric power plants, thermal power plants, engineering thermal
physics, power plant steam generators, automated systems for controlling thermal
proce~ses and of the theoretical fundameritals of heat engineering relating to
studying questions of th~ reliability and ~conomic efficiency both of individual
systems and of modern thermal and nuclear power plant units as a whole.
Included in this collection are the res~ilts of both experimental and theoretical
research covering a broad range of questions relating to the technology, design
and operation of thermal and nuclear power plants. Much attention is paid also
to studying the reliab311ty of individiial nulcear power plant systema and to model-
~.ng dynamic pro~esses originating in tl.lem under transient conditions.
This collection is intended for scient.ific and engineering and technical personnel
_ working on problems of the design and operation of thermal and nuclear power
plants.
UDC 621.311.22
USE OF CHELATES FOR CI,EANING LOW-CAPACTTY BOTLERS AT OPERATING PARAMETERS
[Al~strart of article by Rassokhin, I1.G., Monakhov, A.S., Ryabova, L.V., Dik, V.P.,
Voronov, V.N. and Mayor.ov, M.F.]
(Text] Recommendations are given ~~n the use of chelates (Trilon "B") for cleaning
deposits from the inside heatj.ng surf.aces of low-capacity boilers of the DKVr type,
~ as the result o� washing "in opera~tion," 3.e., without lowering operating para-
_ meters. Washing is achieved by d~lspensing into the boiler's feed water Trilon B
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in a quarit:ity of 1.5 to 2 times the stoich~ometric, for the purpose of combining
witti hardnE~s~ and iron cations present in the feed water, as well as for dissolv-
ing previoi~sly f~rmed deposit~ and converttng them into a complex easily soluble
form conven.ient for the removal of impurities with the blowdown, which is increased
to 10 percent. The feasibility of performing a washing cycle "in operation" for
low-capacity boilers is demo:~strated.
- UDC 621.311.25:621.039
QiJESTTONS RELATING TO TH~ HEAT ENGTNEERING RELIABILITY OF WATER-COOLED POWER
REACTORS
- [Abstract of article by Kabanov, L.P. and Re;Tr.ah= V.]
[Text] Arj. ana~ysis is made of a three-dimensional calculation scheme for estimat-
_ ing heat engineering reliability. The results are given of a calculation for
reactors o~ the WER-440 and WER-1000 type.
UDC 621.311.25:62t.039
ES'iIMA7''LON OT THE PERFOKMANCE RELTABTLITY OF THE SHELL OF A NUCI~EAR i'OWER PLANT
REACTOR
_ [Abstract o:L- article by Kuznetsov, V.D. and Tsimmer, A.]
[Text~ A procedure is presented for calculating the rel~ability of the shell of
a nuclear power plant reactor by using the probabilistic approach. An attempt is
ma.de to take into account the existence r,f flaws in the she11`s ma.terial and the
dynamics of their development. The procedure makes it possible to takP in.to ac-
_ count the influence of such factors as the nature of operation, features.of ef-
�ective loads and embrittlement of the material.
UDC 621.039.53
TWO-NI~TAL CREVICE CORROSTON OF STRUCTURAL STEEL UNDER CONDITIONS OF NEUTRAL
WATER PARAP'~T.ERS WITH TH~ FEEDTNG OF OXYG~N
[Abstract of article by Tolstykh, A.N. and Lipanina, A.A.]
[Text] The results are given of a study of the two-metal crevice coxrosion of
sreel specimens in a loop with the following parameters of the medium: pressure
of 0.6 MPa, temperature of 428 K, traveling speed nf inedium (condensate) of 0.~
- m/s. Oxygen content--0.1 to 0.4 m~Z/kg. The size of the gap in assemolies.was
not grea~er tihan 0.1 mm. Studies were made of specimens of grade 20 steel in com-
_ Uination with s~ee1 of grades OKh18N10T, AS-9 and EP-53 for 1500 h. It is demon�-
strated that the rate of corrosion of grade 20 steel reaches ~,~aximum values of
0.037 g/mZh in c.ombination with grade AS-9 steel minimum values of 0.025
_ g/m?h in contac~ with grade OKh18N10T steel. Pits up to 70 micxons deep were
= present in grad~ 20 steel after testing, and there were nu pits in the other ma-
terials tesCed.
a
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~ UDC 621.311.25:621.039
'
USE OI~ REI,IABILTTY METHODS ~OR A CO'MPARATZ"VE ANAi~XSTS OF NUCLEAR POWER PLANT
SAFETY SY'STEMS
[Abstract of ar'C~~c'le by Kabanov, Z.P, and Makarovskiy, P.L.]
[Text] A comparative analysis is made of the reliability of the emergency cooling
= systems of RBMK-1000 and SGHGJR reactors by means of the Md0001 program, which
analyzes reliability by means of the "Pailure tree" method.
UDC 621.039.53
STUDY OF THE CORROS20N RESISTANCE OF PEARLTTIC STEEL AS APPLIED TO THE OPERATTNG
_ CONDTTIONS OF THE CONDENSATE ~EED SECTTON OF STEAM POWER PI~AN'~'S '
[Abstract of article by Tolstykh, A.N. and Ten, A.] ~
[Text] The results are given of a sCudy of the corrosion resistance of pearlitic
steel in an experimental loop at a temperature of 428 K wi::h a rate of movemen~
of the condensate of 5 m/s for 1500 h. It ia demonatrated that under conditions
= of neutral water parameters with the feedir~g of 10 to 30 ug/kg of oxygen the cor-
rosion of grade 20 steel reaches 0.144 g/m2h.
UDC 621.039.58
_ STABILITY OF A REACTOR OF THE POOL TYPE OPERATTNG UNDER CONDITIONS OF SURFACE
ROILTNG
[Abstract o� axticle by Ratnikov, Ye.F., Vlasov, V.I., Mokrushiy, S.A., Radchenko,
R.V., Shagalov, A.G., Shtoyk, A.G. and Ismagilov, R.Sh.]
[Text] The hydrodynamic stability of the channels of an IW-2 reactor is dis--
cussed. Tt is demonstrated that conditions are possible under which the reactor
operates unstably. The appearance of instability in the core can result in the
origin of heat stresses and the failure of fuel elements. Tt is demonstrated that
for determining the region of stable operation of a reactor it is necessary to
- develop methods of fix3ng conditions for boiling of the heat transfer agent.
UDC 621.311.25:621.039
MODELTNG OF DYNAMIC PROCESSES IN A NUCLEAR POWER PLANT
[Abstract of article by Kuznetsov, V.D. and Romanov, Ye.V.]
[Text] The dynamics of a reactor are discussed, taking into account six groups of
delayed neutrons and reactivity feedback. The results are given o~ the calcula-
tion of some accidental procesaes, ia particular, with de-energiz3ng of the main
circulating pumps.
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T~,~C 621.311.25:621.039
~XPERtMCNTAL STUllX OF THE MCCHANTSM ~'OR EJ`ECT~QN 0~' THE WATER HEAT TRANSPER AGFNT
WITI~ TWO-WAY OUT~'LOW
[Abstract of article by Dement'yev, B.A. and A1'-Bakhili]
[Text] The results are given of an exper3.mental study of hydrodynamic processes
in sudden ejection of the water heat transfer agent with two-way outflow tr~~m a
high-pressure vessel, simulating the shell o~ a water-cooled reactor with intra-
shell equipment. The mechanism for ejection of the boiling heat transfer agent
and the influence of various factors or~ dewatering of the vessel are discussed.
UDC 621.311.25:621.039
D~TI;ItMINATION OF NONSTATl'ONARY '~iATE 0~' FLOW OF A BOILTNG HEAT TRANSFER AGENT
, [Abstract of article by Dement'yev, B.A. and A1'-Bakhili]
[Text] 'The procedure and the results are given of a determination of fihe non-
stationary rate of flow of a boi?ing heat trans~er agent when it is ejected from
a high-pr.essure vessel. An approxima.tion equation which describes the nonstation-
ary z~ate of flow is given.
- UDC 621.039.526.53:669.24
INFLUENCE 0~ NICKEI, ON THE CONVERSTON ~'ACTOR OF T~'AST REACTORS
[Abstr.act of article by Kalafati, D.D. and Groshkov, G.I.]
~ [TextJ A study is made of the influence o~ nickel, contained in the construction
materials of fast reactors, on the conversion factor for several heat transfer
agents. It is demonstrated that the conversian factor is reduced considerably
with an increase in nickel content. The conclusion is drawn that in selecting
construction materials for fast reactors it is desirable to be oriented toward
- grades of steel and al.loys with a low nickel content, especially for steam-cooled
reactors.
UDC 621.311.22:639.025
SUPPLY OF HEAT FROM TH~ PRIMARY CIRCUIT OF WATER-COOLED POWER REACTORS FOR
COVERING THE PEAK HEAT DFMAND 0~' A NUCLEAR HEAT ANA POWER PLANT
[Abstract of article by Abramov, A.I., I1'chenko, A.G. and Kayekin, V.S.]
- [Text] A scheme is presented for covering the peak heat demand of a nuclear heat
and power plant with the heat of the primary circuit of a reactor. Por a nuclea~
heat and power plant with a reactor of the water-cooled pnwer reacfior type, a pro-
cedure is given for determining the amount of ad,justed expenditures for nuclear
fuel tak:Lng into account the change in the heat rating of the reactor and the
size of the reactivity marfiin while holding constant the values of the flow rate
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of the heat transfer agent, the length o~ the reactor's lifetime and the critical
heat demand safety ~actor.
The results of technical and economi.c calculations are preaented.
~ UDC 621.311.22s639.025
- CHOICE OF SEPARATING PRESSURE FOR EXTRACTION TURBINES OPERATING ON SATURATED STEAM
[Abstract of arti,cle by Abramov, A.T., Tishin, S.G. and T1'chenko, A.G.]
[Text] The results are given of calculations for selecting the optimum vaZue of
the separating pressure in systems of nuclear heat and power plant steam turbine
plants of the TK,-4,50/500-65 type, with high attached condensation cagacity.
It is demonstrated that the value of the separating pressure in systems of these
plants can be selected to be the same as for nuclear power plant condensing tur-~
bines .
UDC 621.1:621.311.2
OPTIMIZATION OF DISTRIBUTION OF REGENERATIVE HEATING OF WATER IN A NUCLEAR POWER
PLANT
� [Abstr.act of article by Ryzhkin, V.Ya., Tsanev, S.V. and Sarvate, S.]
[Text] A pracedure 3s discussed for making an analytical determination of the
optimum distribution of the regenerative heating of the feed water of nuclear
steam turbine plants operating on saturated steam. For the sake of comparison,
the results are given of a determinati.on of the optimum distribution of heating
of water by means of alternative cal~uiations.
UDC 621.311.25:62I.039
AERODYNAMICS OF VENT TUBES
[Abstract of article by Gavrilov, Ye.I. and Yakunin, A.V.] �
[Text] In a nuclear power plant radioactive gases are blown off from the equip-
- ment of tha first circuit, pass through a apecial gas cleaning system, are thinned
with ventilati.on air and are emitted in the atmosphere by means of vent tubes.
Aerodynamic systems are suggested for vent tubes which make rare~action possible
over the enfiire height of the gas venting ahaft. ~
UDC 621.311.25:621.039.681.332/333
_ STMiJLA'PTON ON SMALL COMPUTERS IN REAL TIME OF ELEMENTS.AND SYSTEMS OP THE FTRST
CIRCUTT OF .A NUCLEAR POW~R PLANT WTTH 'WER-440 UN~TS
[Abstract of article by Plyutinskiy, V.~., Koloskov, Yu.V. and Gribanova, Z.K.]
5
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~~v~~ va a�a..aria. vu... v.c~.s
[Text] The use of the mode approach to simulat3.ng the operation of a nuclear
power plant wi~.h WER-440 units in creating simulator~ based on sma11 computers
is discussed.
The results are presented of calculations of the dynamic characteristics of
various models oP the WER-440 reactor wi.~h var3ous operating modes of the
- nuclear power plant and the use of a large integration step for differential
equations.
- UDC 621.039.524.44
MATHEMATICAL MODEL OF CIRCULATION DYNAMICS IN A LARGE SHELL-TYPE BOILING WATER
~ REACTOR
[Abstract of. article by Plyutinskiy, V.T. and Leppik, P.A.]
[Tex~] A linear mathematical spatially distributed model of the natural circula-
tion loop in a large shell-type boiling water reactor is discussed. The conditions
for interchannel and loopwide hydraulic stability are formulated.
� UDC 621.176:53.Fi.248.2
PROCEDURE I'OR A CH~CK CALCULATZON OF A COiVDFNSATION INJECTOR
[Abstract of article by Shpil'rayn, E.E., Sevast'yanov, A.P., An, I.V., Buturlinov,
A.V., Grigoryan, A.B. and Solov'yev, A.A.]
[`1'ext] A nrocedure is presented which is constructed on the basis of the experi-
mental data described in the paper. An analysis is wade of the st�ructure of the
flow and of the measured static pressure field, liquid phase velocity and acoustic
characteristics of the stream. The conclusion is drawn that a structural transi-
tion exists from a steam drop flow to a foam bubble one. A system of 18 differen-
tial equations of conservation with corresponding closing rel~~tions is suggested
for the laminar flow section. The systems of equations presented make it possible
- to cal.culate flow parameters in the injector's mixing chamber from assigned initial
parameters and a known geometry. ~
� UDC 621.176:536.248.2
CALCULATION OF TH~ COEFFI�IENT OF VEZOCTTY OF THE MTXII~G CHAMBER OF A CONDi~.NSATTON
- TNJrCTOR WITH CENTRAL rEEDING OF SUPERHEATED STEAM
[Abs~ract of article by Shpil'ra�Tn, E.E., Sevast'yanov, A.P., An. I.V. and
Solov'yev, A.A.]
~Text] The parameters of the main effects determining the value of the coefficient
of velocity of a mixing chamber, Q~k , are discusse~: the shock wave in the region
of the exit section of nozzl~s and ~he shock wave at the center of the mixing
chambc~r. ~'riction losses of the two-phase stream against the channel wal? are
~ calculated, taking into account the diatribution of mixing losses (shock losses)
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- over the length o~ the mixing ~hamber. Qn this basis a seu~emp~,rical relation-
ship is obtained for calculating ~k~ , va11d in general Porm for the cTass of
injectors with the central feeding o~ ~uperheated ~team at supersonic velocity.
= Agreement with the experimental data is sat~sfactory.
UDC 621.039.57g.001.5
STUDY OF THE CONVECTTVE HEAT EXCHANGE CRTSTS IN ~IPES AT LOW VE~OCTTIES 0'~ THE
STEAM-AND-WATER MTXTURE
[Abstract of article by Smirnov, O.K. and Afonin, V.K.]
[Text] The results.are given of a regression analysis of data obtained on the
convective heat excfiange crisis boundary and convective heat exchange coefficients
in the supercritical region wi.th ].ow velocities of the steam-and water mixture in
pipes. A comparison is made of data with a calculation according to the familiar
empirical relationships.
- UDC 621.039.514
PHYSICAL PREMISES FOR ACOUSTICAL DIAGNOSTS OF MODTFICATTON OF FLOW CONDITIOI~S OF
A TWO-PH?,SE MEDTUM
[Abstract of article by Proskuryakov, K.N.]
[Text] The results are given of a theoretical and calculation study of the
dependence of acoustic vibrations in a two-phase flow on flow conditions.
It is demonstrated that an increase in the acoustical capacity of the heat transfer
agent results in the appearance of a negative component of acoustic resistance
and is conducive to the amplification of vibrations.
COPYRIGHT: Moskovskiy energeticheskiy institut, 1980
8831
CSO: 1861/154
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ru~c uhr~~.iAL u5~, uNLY
CONSTRUCTION OF NUCLEAR AND ORGANIC--~UEL~~TRED POWER PLANTS
Moscow STROITEL'STVO '~EPLOVYKH EZEKTROSTANT5TY NA YADERNOM I ORGANICHESKOM
TOPLIVE in Russian No 180, 1980 (signed to px'ess 12 Aug 80) pp 2, 132--133
[Annotation and table of contents from book "Construction of Nuclear and Organic-
Fuel-Pired PowEr Plants", edited by Professor poctor of Technical Sciences
V.B. Dubrovskiy and Assistant Professor Candidate of Technical Sciences N.Ya.
Turi:hin, Moscow Order o~ the Red B~.nner o~ Labor Engineering~Construction In-
stitute imeni V.V. Kuybyshey, 1000 copies, 134 gages]
[Text] Articles are published here, representing the results oi research on the.
protection, strength and economic characteristics oL- construction d~signs of
nuclear and tliermal p~wer plants, and articles devoted to studying the aftereffects
of citemical, mechanical and structural changes talcing place in a number of con-
structi.on materials in the work process, and to study of the technical and economii
indices of the construction of thermal and nuclear power plants.
Intended for scientific personnel and engineer.s specializing ~n various areas
of the planning and construction of power plants, as well as for students
enrolled in the course "Construction of Therma.l and Nuclear Power Plants."
. CONTENTS Page
Koltun, O.V. and Lavdanskiy, P.A. "Determination of the Bulk Weight of
Concrete Shields in Designing the Shielding for Nuclear Power Plant
Technological Equipment" 3
- Koltun., O.V., Lavdanskiy, P.A. and Shekhovtsova, V.D. "Influence of
the Quantity Factor in the Production of Assembly Elements on the Cost
of their Manufacture Under Conditions of the Construction of a Nuclear
Power Plant" 6
Pergamenshchik, B.K., Zholdak, G.T. and Volkova, L.V. "Thermal Condition~
of Shielcling Structures of a Nuclear Power P1ant " 10
llubr.ovskiy, V.B� and Muzalevskiy, L.P. "Decisive Parametexs and Criteria
oC the Radiation Resistance o~ Concrete" 1~
Berman, G.M., Bolberov, A.A. and So1ov'}rev, V.N. "Zn~l.uence o~ Process
Structure on the Radiation Resistance of Epoxy Compositions" 24
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D'yakov, Xe.M. and So1ov'yev, V�~. '~~n~~uence o~ ~xxadiat~,on on
Radiation Aging o~ ~o7.yethylene" 28
Popov, N.N., Zharnitskiy, V.I. and Belikov, A.A. "New 1~ethod. o~ Calculat~
ing Ferroconcxete Strucfiures in the Elastoplastic Stage" 39
Turchin, N.Ya. and Makarin, L.V. '.'~nformation System and System ~or Quality
Control of Work in the Construction and Preparatian ~or Entryr into Service of
Thermal Power Plants" 49
Pavlov, A.S. "Optimization o~ Circulation ~'low Rate at a Thermal Power
Plant with Cooling Towers" ~ 59
Makarin, I,.V. "Designing Series-Produced Thermal Power Plants f~r an
Energy Complex" 6~
Yegorova, M.V. "Some Questions Relating to Specialization of Production" 72
Korsun, Yu.N. and Makarin, L.V. "Influence of Design Solutions for
Boiler Rooms of Series-Produced Thermal Power Plants on Assembly Tndicators
of Low-Strain Beam Systems of High-Capacity Suspended Steam Generators" 77
= Turchin, N.Ya., Ma1'kov, V.V. and Shishkin, V.V. "Procedure for Determining
Actual Specific Labor Costs in Construction.of Thermal and Nuclear Power
Plants" 86
Mal'kov, V.V. and Shishkin, V.V. "Measurement of Labor Productivity Utiliz-
ing Fu11-Scale Indicators" 92
Turchin, N.Ya. "Classification of General Plans and Preliminary Determina-
tion of Areas to be Set Aside for the Construction of Thermal Power Plants
with 300-MW Power-Generating Units" 100
Zmiy, S.N. "Technical and Economic Substantiation of Choice of Optimum
Solutions for a Construction Ma.ster Plot Plan" 108
Volkova, L.V., Pergamenshchik, B.K. and Kim, K.N. "Study of the Character-
istics of High-Plasticity Concrete Mixtures" 113
Pis'menskiy, V.K., Gudin, M.G., Pergamenshchik, B.K. and Spirkin, V.Ya.
"Pressure of a Concrete Mixture" 119
Nictiiporuk, I.I. "Question of the Choice of Designs for Ash Conveyer
Lines for a High-Capacity GRES" 127
COPYRIGHT: MISI ira. V.V. Kuybysheva, 1980
II831 ~
CSO: 1861/149
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UDC 669.018.29:621.039.5/.6
RESEA.ftCH AND DEVELO~'MENT OF MATERTALS FOR NUCLEAR FiTSTON REACTORS
~ Moscaw TSSLEDOVAN:~YE I RA.ZRABOTKA MA.TERIALOV DLYA REAKTOROV TERMOYADERNOGO
STNTEZA in Russi~~i 1981 pp 2, 172^183 ~
I [Annotation and abstracts from collection of articles "Resear.ch and Development
of Materials for Nuclear gusion Reactors'', edited by Academician N.V. Ageyev,
Tzdatel'stvo "Nauka", 183 pages]
. [Text] At the present time one of the most impo~~ant tasks facing our country.'s
scienfiists and engineers is the creation of a new energy base based on the
utilization of thermonuclear power eng3neering.
The creation in the very near ~uture of demonstration and industrial nuclear
fusion reactors with ma.gn.etic and inertial plasma. confinement has already now
become a reality. However, in order to solve these problems it is necessary to
create and study ma.ny classes of construction materials able to function under
the very severe conditions of thermonuclear reactors.
The present collection is made up of original articles on fundamental problems
- of solid-state radiation physics as applied to problems of creating materia.ls
for nuclear fusion reactors, developing construction materials, etc. Individual
sections o~ the co7,leetion are devoted to studying the bulk and sur~ace radiation
properties of various metallic and other materials; also included are original
articles on ~materials-science problems relating to pulsed thermonuclear reactors.
This edition is intended for a wide range of researchers and practical workers
- working on scientific and engineering problems of cnntrolled nuclear fusion.
_ UDC 539.12.04.:621.039.616
STUDY OF THE TNFLUENCE OT ALL~YING ON THE RADIATION RESISTANCE OF MOLYBDENUM
_ [Abstract of article by Ka.lin, B.A., Skorov, D.M. and Yakushin, V.L.]
[Text] A study is made of the cathode sputtering and blistering of grade MChVP
- vacuum-melted molybdenum and alloys TsM10VD, TsM6 and Mo - 0.6 to 2.4 percent by
weight V- 0.03 percent by weight C when exposed to helium ions. Sputtering was
carried out in a low-pressure helium glow discharge and blistering was studied
under exposure ~o a monoenergetic ion beam with energy of 20 keV at a temperature
10
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of 330 K with ~.,dose o~ 5�1017 ions/cm2. Tt fs demonstrated that alloying
rioly~~denum with slight additions o~ vanadium, bvron, aluminum and carbon does not
result in considerable changes in the erosion coeffic3ents of alloys and in
blister-formation parame~ers as campared with pure molybdenum. Increasing the
conCent of vanadium in th~ Mo-V-C system result s 3n some reduction of the a11oy's ,
~ sputtering coeffzcient. ~
UDC 621.039.532.21 ~
RADIATTON ALTERATION OF PROPERTTES 0~' GRAPHITE CONSTRUCTION MATERIALS IN THE
RANGE OF 70-950 �C TO FLUENCE 0~ 2.5�1022 n/cm2
[Abstract of article by Virgil'yev, Yu.S. and Kostikov, V.I.]
[Text] Data are given on radiation alteration of the physical properties (dimen-
- sional stability, heat conduction, strength, creep, etc.) o~ construction graphite
for a wide temperature and neutron fluence range. The influence of several
technological factors in the producfiion of graphite on radiation resistance is
discussed.
- It is suggested that the data presented can be used for a preliminary estimate
- of the working capacity of graphite under conditions of a fusion reactor. Tt is
furtherm~re noted that selection of the optimum working tiemperature in addirion
to selection of the grade of graphite will make it possible to reduce radiation
disturbance of its properties arid at the same time to extend the period for the
- functa.oning of graphite in a fusion reactor.
. UDC 620.172.251.2 .
- PROCEDURE FOR STUDYTNG CREEP OF MATERTALS TN THE PROCESS OF THERMAL CYCLING
[Abstract of article by Skorov, D.M., Kalin, B.A. and Fedotov, V.T.]
_ [Text] As applied to proposed temperature-time parameters of the operation of
fusion reactors, a procedure is suggested for studying creep with the temperature
- changing in cycles, making it possible to conduct tests under temperature condi-
tions controlled with high precision and to compare anisothermic tests with re-
- sults obtained at constant temperatures. A description is given of a high-vacuum
unit, of a model of special design heated by the direct passing of electric
current throu~h it, and of the flowchart of the program for calculating on a
computer anisothermic creep curves, arid the results of a study of niobium a11oy
ELN1 are given.
UDC 621.039.634
PROBTEMS OF CONSTRUCTTON M,ATERTALS ~OR THE ~IRST WALL OF A k'USTON REACTOR
ASSOCIATED WTTH VOT,UMETRxC RADIA,TTON E~~ECTS
[AUstract of article by Kazakov, V.A. and Shamard3n, V.K.J
- 11
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N111K +Ut~'H'1l:lAL U~~ UNLY
[T.ext.~ A review of the published data has establ;Eshed de~inite prpgress both
in del:e:rmination of the probable woxlcing parame~ers o~ the first wa11 in fusion
reactors of vari~us designs and in unders~anding o~ the features o~ radiation
effects which wi11 take place in fusion reactors. The most complicated problems
involve volumetric radiation damage. They are similar to a great extent to those
discovered and studied in sufficien~ detail in ma~erials used in fission reactors.
A who"le series af e~erimental s~udies indficate the possibility of a more drastic
manitestation of some already known prnbZems, such as, for example, high-tempera-
ture ~radiation embrittlement and swelling of nickel-containing steel and alloys
under conditions of the use of the first wa11 of a fusion reactor. These radia-
- tion effects are intensified on accoun~ of the high concentrations of helium
formed in the majori_ty of elements on account of nuclear reactions caused by
neutrons with energy of 1G MeV. The possibil.ity is indicated of realistic tech-
nological and design solutions to a whole series of difficulties in the selection
an~ recommendation of materials for the first generation of fusion reactors.
_ 'Phe complexity of materials science problems associated with volumetric radiation
effects and the diversity of ways of solvir_g them necessitate a comprehensive
approach for the purpose o� finding the most economical and safe variants of
designs for the blanket of a fusinn reactor.
UDC 533.924:539.12.17
STUDY OF PROCESSES OF SUBLIMATION OF SOME CONSTRUCTTON MATERIALS
[Abstract of article by Fedichkin, G.M., Bondarenko, G.G. and Shmykov, A.A.]
['rext] Bp the method of microweighing under high vacuum, measurements are made
of the rates of sublima.tion of grade EP838 and 316 steel, the "Nimonik" alloy
(50 percent gamma phase) and a beta-titanium alloy over a wide temperature range.
Kinetic mechanisms are obtained for processes of the sublimation of volatile com-
ponents from the alloys studied. Tt is established that processes of the subli-
mation of volatile components of these alloys are limited by diffusion of these
components toward the sublimation surface. Individual activation energies are
= calculated. It is demonstrated that the manganese in EP-838 steel (E = 45.7
kcal/mole) is sublimated at the highest rate at working temperatures,aresulting
; in the appearance of impermissible ferromagnetic regions on the surface of the
material. Based on the results obtained, an estimate is made of the contribution
of sublimation processes to the total erasion of construction materials.
UDC 539.12.04:621.039.616
TNrLUENCE OI' T.NTEN5TTY OF ION FLUX ON RADIATION EROSION OF MATERIALS
[AUstract of. article by Ka1in, B.A., Pol'skiy, V.T. and Skorov, D.M.]
[Text] An analysis is made of. the influence of tlie intensity of a beam of light
ions an the heating-up temperafiure of an irradiated target and its radiation
destruct3on as applied to fusion reactors. Heating-up temperatures are calculated
from a four~.h-order heat balance equation for various cases of heat removal of
12
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. . . . ~ . . . _..`9
- the target. An estimate is also u~td~ o~: the possib7.~ migration o~ bubbles of
introduced. gas ~rom the depth to tl~e sur~ace o� the target. ~l'he calculations
- presented de~nonstrate that erosion of the surface on acrount of the gas bubble
migration mechanism depends ~::bstantially on heating up of the target and results ~
- in the appearance of an.et~hed relief in the form of a spongy or acicular struc-
- ture or the surface of the irradiated target.
UDC 539.12.04:621.039.616
_i ~ .
STUDY OF MASS T$ANSFER MECHANISMS IN A'COVERING - GAP - FIRST WALL' SXSTEM
AS APPLIED TO ~'USION REACTORS
[Abstract of article by Kirilin, N.M., Shulov, V.A., Skorov, D.M., Yevstyukhin,
A.I. and Ka~lin, B:A.] .
[Text] A thermodynamic and kinetic analysis is made nf the an alloy-covering system
_ with the presence between them of a gap f:tllec~2with a_rgixture of active gases
(hqdrogen, oxygen, etc.) with pressure of 10 to 10 atm.
Elements with an atomic number of less than 14 and their compounds are discussed
as shielding materials, and alloys based on vanad3um, molybdenum and niobium and
stainless steels as materials for .the first Wai1. It is demonstra~~u that alloy-
ing high-melting metals with Ti arid Si (for niobium) suppresses the mass transfer
of atoms of alloys to the covering over the 800-1200 �C temperature rnage. From
the viewpoint of mass transter, of the shielding materials considered preference
is to be given to compounds based on aluminum.
UDC 533.924:539.12.17.
DEPENDENCE OF RADIA.TION EROSION OF OKh16N15MZB STAINLESS STEEL ON THE DOSE
I~I IRRADIATION WITH HELIUM IONS WTTH ENERGY 0~' 20 keV
[Abstract of article by Ka.lin, B.A., Kirilin, N.M., Skorov, D.M. and Chernov, I.I.]
[Text] A study is made of the radiation erosion of OKh16N15MZB stainless steel
in the austenitized and 20-percent cold-strained states when irradiated with
helium ions with energy of 20 keV at 200 �C over the dose range of (10 to 500)�
�1021 ions/m2. It is demonstrated fihat in the dose range studied the maximum
er.osion coefficient was on the order of 0.5 at/ion when irradiating with a dose
of 1�1022 ion/m2 and was reduced~with an increase in the ion dose. With irradia-
tion doses higher than 2�1023 ions/m2 the total erosion coefficient practically
equals the steel's sputtering ratio. The influence of pretreatment on erosion of
the material is reduced with an increase in dose and is practically lacking with
high irradiation doses of (4 to 6)�10~2 ions/m2.
~UDC 669.27:537.534.9
FIELD-TON AND ELECTRON MTCROSCOPE STUDY OF THE SURFACE OF TUNGSTEN TRRADTATED
WITH HELIUM TONS ~ ~
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� V~� v~ ~ Y~.~1~u ~+vwe V1~u�
[Abstract of article by Dranova, Zh.I., M~:khaylovskiy, I.r1., ~ivovar, L.I. and
- Tostolutskaya, G.D.] ,
[Text] By the methods of electron and field-ion microscopy studies were made of
changes in the structure and microrelief of the surfac~ of tungsten under the
- effect of irradiation with helium ions. A study was made by means of an electron
microscope of. the influence on blistering of the original structure o~ the mater~
ial formed as the result of �rollf.ng and recrystallization annealing.
Comparison of structures formed on the surface of tungsten as the result of
irradiation at room temperature and as the result of irradiation with subsequent
annealing demonstrated that no substantial d3.fference was observed in the nature
of scouring. Measurements were made of the thickness of the scoured layer as a
- function o~ tha ion energy and a comparison was made of the thickness of covers
with calculated values o~ the mean free paths of helium ions in tungsten.
By means of a field-ion microscope a study was made of the atomic topography
- of single crystals of tungsten irradiated wi.th helium ions with energy of 0.1
to 3.0 keV over the dose range of 1011 to 1017 cm 2. Tt was established that
with an irradiation dose of 1011 to 1012 cm 2 the change in microtopography as
~he result of the radiatio~? effect is two orders of magnitude greater than the
form-alteration effect caused by~ erosion. Early stages of blister formation
were observed with doses of 101 cm 2 and higher; the blisters measured 102 to
- 1U3 t~. A study was made of the microstructure of irradiated tungsten by means
of the method of field~controlled layer-by-layer sublimation.
UDC 533.924:539.12.17
= MAGNETO-OTPICAL STUDY OF ISOLATION OF THE ~ERROMAGNET,IC PHASE ON THE SURFACE OF
SOME CONSTRUCTION MATERIALS FOR FUSION REACTORS
_ [Abstract of article by Krincha.k, G.S., Nikitin, L.V., Bondarenko, G.G. and
Fedichlcin, G.M. ]
[Text] By the ma.gneto-optical method a study is made of isolation of the ferro-
magnetic phase on the surface of chrame-manganese austenitic steel after various
kinds of heat treatment. 'rhe ferromagnetic phase was not detected on the original
samples which had been electropoli~hed, but after vacuum annealing the appearance
of a ferromagnetic alpha phase was observed caused by the sublimation of austen-
itized components. Quantitative characteristics of the selective sublima.tion of
these components are given, obtained by the method of microweighing under high
. vacuum. For the purpose of studying the kinetics of the alpha phase formation ~
process taking place, temperature measurements were made with a specially created
- ma.gneto-optical apparatus making it possible to study surface magnetic character-
istics under conditions of high vacuum and high temperatures. A comparative ana-
lysis is made oi processes taking place in materials of various compositions
and the poss3bility is indicated of the appearance of a thin ferroma.gnetic layer
in the course of utilization of tl~e first wa11 of a reactor. ,
1~. ~
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UAC 662.747:546.17.:533.9;537.525
- INTERACTION OF CARBON (GRAPHTTE AND DTATZONA) COATI'NGS WTTH THE HYDROGEN PLASMA
OF A GLOW D'tSCHARGE
[Abstract of a~t~cle by ~'edoseyev, D.V., Deryagin, B.V., Tolmachev, ~(u.N.,
~ Bukhdvets, V.L., Varnin, V.P. and Teremetskaya, T.G.]
[Text] It has''been proven that the application of a coating of an acetylene-
- hydrogen plasma~-to char substantially reduces the rate of gasification of the
char in a hydrogen plasma~ The dependence of the rate of gasification of a
- carbon coating in a hydro~en plasma on the temperature has a 550-900 �C section
in which the reaction rate is reduced with an increase in temperature. The
depth of. penetration of the reaction into a layer of diamond powder coated with
graphite does not exceed 1 mm with a particle size of 100 to 125 microns, which
~ is associated with the rapid recombination of hydrogen atoms in the powder layer.
~ In the interaction of polycrystalline graphite with a hydrogen plasma. the amor-
_ phous component is gasified first, whereas graphite crystals are gasified at a
considerably slower rate.
UDC 539.9.082:533.924
BLISTERTNG IN VANADIUM WITH SUCCESSIVE IRRAi)IATION WTTH HYDROGEN AND HELIUM TONS
[Abstract of article by Guseva, M.I., Z}rkova, N.M., Ionova, Ye.S., Koltygin, V.M.,
Krasulin, Yu.L., Kurakina,.T.S., Nedospasov, A.V. and Rozina, I.A.]
[~ext] A study is.made of the influence of preliminary and later implantation of
H ions on helium bl3stering in monocrystalline vanadium. The considerable in-
fluence of irradiation with hydrogen ions on erosion of the surface has been
proven and the introduction of hydrugen causes embrittlement of the surface of
vanadium, resulting in the opening of blisters along the outline of.shells.
UDC 621.032.573
MATERIALS SCIENCE QUESTIONS IN THE PROBLEM OF PULSED FUSTON REACTORS
[Alistract of article by Gryaznov; G.M., Yevt3khin, V.A., Kosukhin, A.Ya., Zanegina,
O.A., Mosin, A.P. and Gurov, A.D.]
[Text] Factors of the effect of a thermonuclear microexplosion on materials of
the first wall are discussed in condensed form. Key trends of studies relating
- to the theoretical and experimental investigation of materiala are indicated.
tTDC 533.924:539.12.17
STUDY aF THE PROCESS OF BLISTERTN~ QF ALUMTNUM AND STAINLESS STEEL IN IRRADIATION
WITH HELTUM IONS '
[Abstract of articl,e by Bondarenko, G.G. and Vasi1'yevski}~, V.V.]
i5
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,~~~rc ~~rre~.iwa, u~a v~v,~r
[Texr] An e].ectron ~nicroscope study is ma,de o~ erosion o~ the surface o~ poly�-
crystal.line aluminum, and s~afnl.ess steel of austenitic class E~--838 under the
effect o~ helium ions with energy af 10, 20 and 175 keV. The ~ma.terials were
irradiated in the "Vezuviy" [Vesuvius~ heavy ion accelerator, as we11 as dire.ctly
in the column of an EF2-Z6 field-emission microscope by means of a special
attacliment .
A study is made of the influence of postradiation annealing on the nature of
- form modification and scouring of the surface of EP-838 steel. It has been
pr.oven that lncreasing the temperature of the irradiated sample to 1200 �C re-
sults in an approximately sevenfold increase in the surface erosion coef~icient.
A study is made of the inf.luence of ~article energy and the irradiation ~ose
on the nature of radiation damage to ehe surface in polycrystalline alumtnum.
Tt is demonstrated that with 1ow energies of helium ions (5 to 10 keV) the domi-
nant process is physical erosion. c~f the irradiated surface, and with increased
_ ene~gies (20 to 30 keV) the blistering effect. Tn the 5�1017 ta 1.7�1018 ions~
/cm` range increasing the 3rr~diation dose results in an increase in the surface
- erosion coefficient by more than an order of magnitude.
~ UDC 620. 19
MATERTALS SCTENCE QUESTIONS RELATIIVG TO CRFATTON OF LIQUTD METAL SYSTEMS ~OR
PULSED FUSION REACTORS
[Abstract of article by Gryaznov, G.M., Kosukiiin, A.Ya., Koloskov, D.M.,
' Loseva, N.V. and Yevtikhin, V.A.]
(Text] Possible corrosion processes in a construction material - lithium system
are discussed. The influence of various factors responsible for the per.~etrability
of an alkali metal and corrosion is demonstrated.
A determi:nation is made of the necessary cAnditions and technolog3.cal requirements,
confirmed by fuil-scale circuit tests, making possible the reliable working
capacity of materials of liquid metal systems with lithium.
- An analysis is made of working conditions for ma.terials of the blanket zone of
_ a pulsed fusion reactor. The possible in~luence of factors of the microexplosion
of a D-T target on the materia'ls af the first wa11 and blanket zone is demon-
strated. The key trends of studies relating to materials science research are
_ delineated.
UDC 539.12.04:621.039.616
STUDY OF RADIA'I'TON EROSION OF MATERIALS TN CYCLIC IRRt~DIATION WITH IONS
~ [Abstract o~ article Uy Begrambekav, 7.,.B., Kalin, B.A., Korshunov, S.N., Skorov,
D.M., Skulanov, S.B., Te1'kovskiy, V.f~. and Yakush3.n, V.L.]
[Text] A study is made of the radiation blistering of grade NIChVP molybdenum and
grade VE;L-2 vanadium c~hen irradiated with helium ions with energy of 20 keV
16
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in a dose o.~ 2~IO1e ions/cmZ over a wide rang~ o~ $ngles o~ incidence of ions
and with a cyclic mode of irradiation. Simulation o~ the range of angles of
incidence o~ ions is accomplished by~ evenly turning the target in the process of
irradiation around an axis perpendicular tc~ the incident ion beam. It is demon-
strated that the irradiation. of materials oti�er a wide range of angles of incidence
of ions resul~s in reduction o~ the eroston c~efficients of the materials because
~ of the breaking of blisters and changes in blir~ter formation parametera.
.
UDC 539.234
PASSING 0~ BEAMS OF HTGH-ENERGY ELECTRONS THROUGH A QRAPHITE FOTL
[Abstract of article by ~'edoseyev, D.V., Vnukov, S.P. and Statenkova, Ye.V.]
[Text] Graphite foil--a material produced as the result of '.:he pyrolysis of
methan~ and axPtylene--is vacuum tight and thermally stable and therefore ca~n be
- recommended for the windows of high-energy electron accelerators.
A calculation pr~esented ~f the passi:~g of a fairly powerful beam of relativistic
- electrons (approximately 2 MeV) through graphite foil has demonstrated that
it can transmit pulses of up to 3�109 J/m2.
UDC 539.121.72
- HIGH-INTENSITY NEUTRON GENERATORS
[Abstract of article by Tel'kovskiy, V.G.] ~
[Text] Methods of produc3ng intense (greater than 1013 n/4~r) neutron flux with
energy on the order of 14 MeV are discussed. Circuits of neutron generators
with these parameters developed in our country and abroad are analyzed, utilizing
the reaction for the fusion of deuterium and tritium ("solid.state" and "gas"
- targets) and the reaction fo�r fusion of lithium-7 a.nd deuterium.
In the case of neutron generators with a solid-state target (ions of deuterium
irradiate a metal target saturated with tritium), design solutions for neutron
- generators are di.scussed, as well~as the physics of processes taking place on the
irradiated surface (including queations relating to confining the tritium in the
target).
Tn the case of a gas target (ions of deuterium bombard a supersanic stream of
~ tritium), processes of heat transfer from the reaction zone, the problem of
the entry of a powerful ion beam into a dense gas target and poasible design sa-
lutions for neutron generators axe discuased.
Possibilities of the ~reation and the features of neutron generators with a
lithium target are discussed and the posa3.ble circuit of a neutron generator is
given.
Based on an analysis o~ the results, directfions of �uxther studg required for
_ the creation of high-intensity neutron generators are pointed out. .
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UDC 533.2
PROCL'SSES OI~ A~F'EC`~ ~01~'1~TTQN A~I`TA AI"~T~'iTSZON TN MOLY~DENUM UNDER CQNDTTTONS OF
IRRADIATION WT~H I,OW~~.NERGY It,~N~ QF HX'DRQGEN, 'DFTJTER~VM AND HEI~TUM
[Abstract ofl articl.e by Zakharov, A.P.]
~ [TextJ By nieans o~ electron microscope methods, structural changes are: traced
in surface lapers o~ molybdenum irradiated with 1ow-energy hydrogen io~~. In
studying processes of the penetration o~ hydrogen through a metal unde~~ conditions
of the piasma. of a glow discharge, the e~fect of the radiation-accele,rated diffu-
sion of hydrogen has been discovered, caused by fihe formation o~ an internal
inter.stitial atom - hydrogen atom dynamic complex with a dissociation energy of
- ~ approximately 2 e'V. New possibilities for studying the distribution of light
implanted ions are offered by the method of layer-by-layer analysis by means of
erosion with argon ions. Because of its application it has been possible to
fix the position of l.ons in the lattice of a metal with various irradiation tem-
- peratures and to reveal the phenomenon of the redistriUution of helium found in
- vacancies as the result of reaction with SAM-N complexes.
UDC 681.32:548.4
INFLUENCE ON HARDENING OF THE ALTGNPIENT OF RADTATTON DEFECTS IN THE SUPERLATTTCE
_ [~.bstr.act of article by Ibragimov, Sh.Sh., ICirsanov, V.V. and Tyupkina, O.G.]
_ [Text] By means of a modified ~"ormen-Meykin model the particular case of the
dis~ribution of radiation defects in front of a moving dislocation is discussed,
namely, their ordered arrangement (the so-called superlattice of defects).
Since de:Eects in experimentally observed superlattices are nonur_3form in size,
it is to be expected that in interaction with a moving dislocation they wi11
behave differently. Within the framework of the model used an attempt is made
to take thls effect into account, by introducing two sizes of point obstacles
and distributing them randomly over points of the superlattice.
UDC 620.193.6:539.219.3
RESULTS OF STUDYING TH~ PROPERTTES OF NTCICEL=FREE STATNLESS STEEL UNAER CONDTTTONS
CHARACTERTSTTC OF A 1~USTON REACTOR
[Abstract of article by Barannikova, G.A., Vaulin, L.N., Gol'tsov, V.A., Guseva,
M.T., Latyshev, V.V., Prokof'yev, Yu.G., Saksaganskiy, G.L., Sotnichenko, A.L.
and I'efelov, P.A.]
[Text] The results are presented o~ studies of ~he properties of chrome-manganese
steel 06Kh17G17llAMS (AS9) and 06Kh17G15NAB (AS43) performed in connection with
stl~dying the poss:i.bility of us3ng these steels in designs of fusion reactors.
In particular, experimental da~a are presented on the change in the mechanical
characterisrics o:~ these stPels 3n the temperature range of 20 to 700 �C after
being irradiated w~tb.fast neutxons (dose of 8�1020 n/cm2, ~.rradiation
- 18
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tempexature a~`65Q �C) and on a~~udy~o~ shoxt~t~u~e ~ar~gue ~n Che 20-600 �C ~
temperature range undex vacuu~n and ~n fiydrogen.
Data aze a:Cso presented on the erosion reais*ance o~ the steels studted when
irradiated with hydTOgen and he7,:tuzn ions and on their gas di~fusion and magnetic
_
characteristics. .
UAC 539.9.082:533.924
PROBLEMS REZATTNG TO TIiE PTRST WAZL OP :E'USTON REACTORS
~ [Abstract of ar*.ic1e by Guseva, M.T., Martynenko, Yu.V. and Plesh3.vtsev, N.V.]
[Text] ^4ajor processes on the surface of the first wall o~ a thermonuclear
reactor--a tokamak--are discussed. A calculat3on is made of the rate of ero~ion
o~ the wa~l of a T-20 tokamak under Che effect ot' bombard~ng ions (atoms), D,
' T and He . Tt is demonstrated that the main physical process responsible for
e~osi~n of th~ surface of the firat wa11 is erosion of the wa11's material by
D, T and He ions. Ways of protecttng the first wall from erosion are discussed.
UDC 539.9.082:533.924
STUDY OF EROSTON OF THE SURFACE OF CHROME-NICKEL ALLOYS IN BOMBARDMENT WTTH
HELTUM AND HYDROGEN IONS
[Abstract of article by Busharov, N.P., Gusev, V.M., Guseva, M.I., Ionova, Ye.S.,
Mansurova,.A.N., Chelnokov, O.T., Afrikanov, T.N., Morozov, V.N. and Fefelov, P.A.]
[Text] Studies are ma.de of radiation damage to the sur~ace of Fe-Cr-Ni alloys .
- in bombardment with ions with energy o� 40 keV at various temperatures. At
~ Tirr re~iond - 200 �C scouring of layer.s is observed and the erosion rate
reach~s ppr ximately 1 at/ion, and at 500 �C blisters form on the surface.
- Maximum erosion of the surface. takes place at Tirr about 39~ of inelting point."
Erosion cuefficients of these alloys are measured for ions wi~h energy of 10 keV.
~ UDC 621.791.85:669.018.8
ROLE OF RADIATTON-STTMULATED PHASE TRANSFORMATTONS TN CHANGING OF THE PROPERTIES
OF FUSION REACTOR MATERIALS
[Abstract of article by Bystrov, L.N., Ivanov, L.I., tTstinovshchikov, V.M. and
Tsepelev, A.B.]
['i'ext] The question of the influence of radiation-stimulat~ed struc~ural phase
transEormations on the mechanical properties of fusion reactor construction ma-
tE~rials Is discussed. A study is made of grades 316 and EP838 stainless steel.
A study is made o~ the kinetics of a change in the electrical resistance of
316 steel under the effect of electron irradiation with energy of 2.3 MeV in the
temperature range o~ 100-400 �C and the possible mechanism for changes observed
in electrical resistance is discuesed. 8y the actfive tens3on method and a
stud.y of creep a measurement is made o~ the mechanical characteristics of 316 and
_ ~9
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EP838 steel. irradiafied with electrona in ~he austenitized and cold-strained
states. The conclusion is drawn th$t there i~ the pc+s~ibility o~ ~the con~iderable
influence of radiation-sti~nula~:ed di~~'us3.on processes on changing of the properties
of austenitic stainless steel in the process of operation of a fusion reactor.
UDC 533.924:539.12.17
STUDY OF RADTATTON EROS~ON 0~' N~OBTL'21 AZLOYS
' [Abstract o~ article by Ka1in, B.A., Skoxov, D.M. and Shishkin, G.N.]
- [Text] An electron m3.croscope study is made of failure in ion bombardment of
the surface of alloys of the system Nb-Zr-C having undergone tests for 1-percent
creep in Li. irradiation was with helium ions with energy of 15 ke~F over the
= dose range of (0.5 to 10)�1018 ions/cm2 at 700 �C with a beam current of 0.4 mA/
/cm2 Tt is dem;:ZStrated that the ~rocess of blister forma.tion takes place
with doses of (5 to 10)�1017 ions/cm' and practically does not depend on the tech-
nological characteristics of the alloy. With an increase in the dose to 5�1018
ions/cm2 and more radiat~.on erosion is determined basically by sputtering.
- The alloys tested prior to irradiation ~or an extended period under a load in
lithium tend toward 1oca1 erosion with th.e formation of craters measuring 200-
700
UDC 620.17:537.534
COMBTNATTON OF EXPERIMENTAL APPARATUS ~OR STUDYTNG RADIATION-VACUUM AND PHYSICO-
MECHANTCAL CHARACTERTSTTCS OF ~'[JSTON REACTOR CONSTRUCTION MATERTALS
[Abstract of article by Karasev, B.G., Komarov, V.L., Prokof'yev, Yu.G.,
Saksaganskiy, G.Z., Serebrennikov, D.V., Spirchenko, Yu.V. and Fefelov, P.A.]
- [Text] A brief description is given of the designs and technical chara~:teristics
of experimentation stands for study~ng erosion resistance of the sur~ac~e., water
tightness at high temperatures and the mechanical characteristics under conditions
of. static and cyclic straining, of const.ruction materials whieh are promising for
use in fusion reactors.
The SVICh stand has a hydrogen ion source with energy from 20 to 80 keV, current
density of the beam at the tar~et of 0.01 to 0.1 A/cm2 and background pressure in
the measuring chamber of 1�10 ~ mm Hg. .
The MKT stand has been created �or irradiating materials with ion beams with
a mass spectrum from 1 to 40. The ion energy is 0.1 to 20 keV, the beam current
is a maximum of 5 mA and the background pressure in the target chamber is 1�10-10
mm Hg. The posslbility 3s provided of irradiating the target simultaneously with
two ion beams vf di~feren~ types.
The TYeST and LUCh stands are designed ~or studying the water t~.ghtness o~ mater-
ials at high temperat'urea, including by takfing into account nonequil~bxium con-
ditions and the stxes~ed-strained s~ate o~ the mater~;a1.
20
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The Ts~KT., stand has b~en crea~ed ~ox aCudy~~ng tlt~ ~:n~l.uence an tna.ex~als of
- static and cyclic mechan~ca7. ~.oads a~ ~var~ous t~ntpera~ux~s~ ovex ~he range of
-260 to 1Q00 QC. 7.hvestigation o~' the behavfox o~ u~tterfials wfith vartation in
strain ~orces and temperatures o~ samples accord~ng to a specif:ic program 3s
p~evided for. ~
- UDC 539.9.082:533.924
INFLU~NCE OF ORIENTATTON ON ~ROSTON 0~ MONOCRY~TALLTNE VANAAZUM UNDER BOMBARDMENT
WITH HELTUM TONS
1 [Abstract o~ a~ticle by Guseva, M.T., Zykova, N.M., Tonova, Ye.S., Koltygin, V.M.,
Krasulin, Yu.Z., Kurakina, T.S., Nedospasov, A.V. and Rozina, T.A.]
[Text] Studies are made of radiat~on damage to the surface of monocrystalline
- vanadium under bombardment with He ions with energy of 10 and 40 keV. Tt is
de~onstrated that with a dose of 0.5 curies/cm2 in the case of irradiation with
He ions with energy of 10 keV, on a{100}, {111} and {110} surface bli~ters are
formed with undamaged sizells, whereas after implantation with 40-keV He ions,
other condi~ions being equal, on these planes mul.tilayer scouring is observed,
and strorig anisotropy of blistering and flaking occurs.
- UDC 621.039.553
PROSPECTS FOR USING ALPHA ALLOYS OF TTTANZUM AS A CONSTRUCTION MATERIAL FOR THE
FIRST WALL OF THE ZOW-TEMPERATURE DISCHARGE CH1~IMBER OF A FUSION REACTOR
[Abstract of article by.Al'tovskiy, I.V., Gorynin, I.V., Kozhevnikov, O.A.,
Lemke, N.G., Od:Lntsov, N.B., Odintsov, V.N., Parshin, A.M., Privol'neva, A.S.,
Syshchikov, V.T., Ushkov, S.S., ~efelov, P.A., Chechulin, B.B., Yakovleva, T.A.
and Yaroshevich, V.D.] ~
[Text] The results are presented of a studq of grade VT1-0 technically pure
titanium and of the alpha alloy PT-7M in the original state and after neutron
irradiation with fluence up to 2�1021 n/cm2 (E > 0.85 meV). It is demonstrated
that the alloys studied possess h3.gh radiation resistance and preserve their
ductile properties at a suf~ic3.ent 1eve1 both under short-term and extended test-
ing. The conclusion~is drawn that in terms of combination of physicomechanical
properties low-a11oy alpha alloys of titanium.satisfy the requirements imposed
on construction materials for d3scharge chambers of fusion reactors and are pro-
mising for use in these structures. ~
UDC 533.924.:539.12.17
HTGH-NTCKEL ALLOYS OF THE CHS-42 AND CHS-43 TYPE AS MA.TERIALS FOR THE FTRST WALL
OF FUSTON REACTORS
[Abstract o~ article by BannykYt, O.A., ~oryn~n, T.V., Ibragimov, Sh.Sh., Tvanov,
A.T., Kozhevnikov, O.A., Lapin, A.N., Lopatina, O.A., Makhlin, N.A., Parshin,
A.M., Pen'kov, G.A. and Y'aroahevich, V.D.]
21
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~'Uii U~FIQ:~AL ~15~ UNiY
['tex~1 ~1u;~~ti.ozls ~xe di~cuas.ed r~la~in~ ~o u~i.ng h~,$h-~icke7, a7.7.oys o� the
ChS-~+2 r.ttzd ChS-43 ty~e. as constxu~w~:on mat~x~a7.s ~px ~he ~irS~ wa~~ o~ a~usion
reactor ovex a hroad temperature xange, Aata are presented on the xadiation
resistance ox these alloys, ob~ained on the basis of both reactor and simulation
tests. Thes