SCIENTIFIC ABSTRACT KOMAROVSKIY, A.A. - KOMAROVSKIY, L.YE.

• Document Type: CREST
• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R000824110012-2
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 100
• Document Creation Date: November 2, 2016
• Document Release Date: June 14, 2000
• Sequence Number: 12
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

SOV/12I4-57-8-9ZO9
Translation from: Referativnyy zhurnal. Mekhanika, 1957, Nr 8, p 91 (USSR)
AUTHORS: KomarovskiX, A. A.,._Verte5hev, M. S., Strelltsov, V. V.
TITLE: The Hydraulic Resistance of a Layer Consisting of Particles of
Arbitrary Shape (Gidravlicheskoye soprotivleniye sloya chastits
proizvol,lnoy formy)
PERIODICAL: Tr. Novocherkas. politekhn. in-ta, 1956, Vol 41 (55)~ pp 41-57
ABSTRACT: The resistance of a layer consisting of particles of arbitrary shape
can be expressed in terms of the resistance of a layer consisting of
equidimensional spherical particles with the use of a so-called layer
coefficient. A sur'vey.is made of the results of numerous investiga-
tions on the resistance of a layer, wherein the formulas propounded
by th e various authors are provided in terms of a consistent system
bf parameters. Test results obtained by the authors with respect to
the measurement of the resistance offered by layers consisting of
aluminum cylinders (4 specimens) and of sand particles 0,45, 0.90,
1.80 mm are'adduced. fn their analysis of the test results the authors
employ a well -subs tanti atdd formula of the type
Card 1/2 + b (where R is the Reynolds number).
R

SOV/124-57-8-9209
The Hydraulic Resistance of a Layer Consisting of Particles of Arbitrary Shape
For the layer consisting of spherical particles they employ the formula
0 IL~ + 0. 9
R
which differs only in the magnitude of the free term from the formula previously pro-
posed by N. M. Zhavoronkov (Zhavoronkov, N. M., Aerov, 'M. E., Umnik, N.'.-N.,
Zh. fiz. khimii, 1949, Vol 23, Nr 3, p 342). Values of the layer coefficient obtained
in seven tests by the authors are presented in tabular form. Bibliography: 23 ref-
erences.
Ye, M. Minskiy
Card 2/2

Krjmf)~ov~roy,A4
AUTHOR: Komarovskiy, ~Iandidate of Technical 64-58-3-12/2o
8,__ I t sov 0
Sc=enc-e Stral V. V.
TITLEt On the Computation of ~the Optimum Working Regime of filters
With Per4odio Action (0 raschete optimallnogo rezhima' raboty
fil'trov periodicheskogo deystyiya)
PERIODICAL: Khimicheskaya Promyshlennost', 1958, Nr 3, pp 0-48 (USSR)
ABSTRACTs It is stated that the computation equation of Rhodes (Rof 1)
can be employed for the first period of scavenging by pressing
out the liquid, but not for the second period which was re-
ferred to as diffusion scaven- ing, as there is really no con-
.g
siderable effect of the diffusion on the scavenging as was
proved by experimental data. Starting from the assumption that
residual quantities of the mother liquor remain.in the compara-
tively large cavities of the Svitlend filter it is supposed in
the present paper that these quantities are mixed up with the
scavenging liquid and thus a solution of variable concentra-
tion is scavenged. According to the law of changes in concen-
tration in dissolved substances considerations and computations
Card 1/2 are given which prove that there are three periods. The compu-

on the Computation of the Optimum Working Regime of 64-58-3-12/2o
Filters With Periodic Action
tation equations and results inferred from that which are
based on a laminar flow of the liquid in the canals of the fil-
ter cake are confirmed by the investigation results of Crosier
and Brownell (Ref 11), and on-the other hand render it possible
to compute the optimum regime of the filters mentioned in the
title above. With that the computation method remains the same
as before, but the function of the coefficient of the scaven-
ging conditions A (which corresponds to one of the thr 11 e periods
in which the termination of the scavenging takes place) of the
ratio V/Vo must be considered. For the latterseparat* equa-
tions are given each of the three periods. There are 12 referen-
ces, lo of whioh are Soviet.
1. Particulate Pilters--Performance 2. Mathematics
Card 2/2

KMR nd ic- STRILITSOV, VoV.
5jN4AAI -w-114 - tekhu. nsu] ,
O-OW-- I . -
Calculating optimum operating conditions for intermittent filters,
Mime prom. tkoo3:173-176 AP-My 158. (NIRL 11W
I (Filters and filtration)

STRELITSOV, V.V.;-KOMAROVSKIY, A.Ae, kAnd.tskhn.nnuk
Mass transfer from a statlonsr7 granular layer to floving liquid. .
Xhim, nauka i prom, 3 no.4:511-519 '58- (ITIRA 1410)
(Mass transfer)

KOMAROVSKIY, A.A.; STRILITSOV, V.V.; VIMWHEV, M.3.
Inves4igating miss transfer during the dissolution in fixed and
fluidized beds. Isv.vye.ucheb.zav.; khimA khim.tekh. 2 no-5:
810-817 159. (MIU 13:8)
1. Novocherkasokly politakhnichookiy institut, kafedra, tekhnologil
neorganichookikh vashebeety.
(Mass transfer)

o622
28(5) sov[94-59-6-20/28
AUTHORSs Komar Vertashey, X. S., Docent,'Candidate of Tech-
;~nical Sciences
TITLE: gn the Intensity of Mass Transfer in the Dissolution in an
Immobile and Suspended Layer
PERIODICAL: Khimicheskaya promyshlennost', 1959, Nr 6, PP 530'- 533 (USSR)
ABSTRACT: It has been stated (Ref 1) that the coefficient of.mase trans-
fer in an immobile layer is greater than in a suspended one.
This holds for the coefficients of heat and mass transter in
the case of small particles, while in the case of bigger partic-
les the heat transfer coefficient is greater in a suspended
layer than in an immobile one (Ref 2). The authors of the paper
under consideration carried out investigations of the dissolu-
*;ion of salts in immobile and suspended layers (Refs 8112) and
derived the corresponding equations, (1) and (2), which have
been proved to hold by the experimental results obtainqld with
systems R&C1 - water or CUS04.5H2O - water (Equation (1)) and
systems NaCl KN031 CuS04-5H2O - water (Equation (2)), respecti-
vely. The ma;s transfer coefficients.N for the immobile and
suspended layer are derived from equations ~1) and (2), and the
intensity of mass transfer in the two cases is studied by means
Card 1/2 of the example of common salt at 180. The dependence of A on

o6228
On the Intensity of Mass Transfer in the Dissolution SOV/64-59-6-20128
in an Immobile and Suspended Layer
the rate of filtration wf and the particle diameter d was in-
vestigated. kn increase in wt has a greater effect upon
in the immobile layer than in the suspended layer (Fig 1 ~. An
increase in d results in a lowering of ~f in the immobile layer,
while increases slightly in the case of the suspended layer.
In ordt to assess the effective use made of the space units
available in the apparatus the value P. rather than 13f has to
be used, which refers to one unit of space of the layer. In ves-
tigations of the dependence of v on wf and d show that 4 de-
A m A,
creases in the suspended layer and increases in the i m le
layer as wf increases (Fig 2). The dependence of the mass trans-
fer coefficient Pl, which takes into consideration the loss of
work (due to the overcoming of the hydraulic resistance), shows
(Fig 3) that in the suspended layer Pi greatly decreases as the
particles become bigger, while r4 in the immobile layer does
not so much depend on the partible size. There are 3 figures
and 16 references, 10 of which are Soviet.
Card 2/2

__ STMITSOV, V.V., 1mnd.tekhn.nauk; KOMAROVSKIY. A-A-, kand.tekhn.nauk
Calculation of a CODtinuOus apparatus for discolving malt in a
statiouar7 bed. Rhim.prom. no.7:624-627 O-N '59. (MIRA 1315)
(Salt) (Solubility)

) and STRMITSOV) V. V.
KOMAROVSM, A. A.
118uperposition of Naturtl Convectlon on Forced one at
Mass Transfer in a Liquid Flow Through an Immovable Granular
Layer,"
Report submitted for the Conference on Heat and Mau Transfer,
Minsk, BSSR,*June 1961.

KOMARO �19L, A.
--
Continuous ion exchange process in ste6ed-countercurrent type
apparatus with a fluid bed of ion exchanger. Zhur.prikl.khin.
36 no.6t1217-1223 36 no.6sl217-1223 Je 163. (MIRA 160)
1. Novocherkasskiy politekhnichookiy institut imeni S.Ordshonikidso.
(Ion exchange) (Fluidization)

KOMAROVSKIY A A
Rquations of the ionic balance and the ki4ptics of mass transfer
in a continuous process of ion exchange in a stage-countercurrent
type apparatus with a fluid ion exchange bed. Zhur.prikl.khim.
36 no.6:1224-1231 A 163. (MIRA 1638)
1. Novocherkasskiy politekhnicheskiy institut imeni S.Ordshonikidso.
(Ion exchange) NABs transfer) (Fluidization)

L 1296MI
-ACCESSION M: AP3000399
ATMOR: vorteshey, bi. s.; komarovskiy, A.
TIMJ~ Hydraulic classification of i resins
on-exchange
SOMCE Plasticheskly~e no. 5*1963, 32-36,
I assification, ion-exchazige mids,. hydraulic sorter
PIC TAGS: hydraulic cl
M
:;ABSTRACT: The construction and "eration, of an inprcnred direct-acting, suspended-
,:layer hydraulic sorter are described and, illustr~ated .(see' Figure 1, Enclosure I ands
caption, Enclosure 2). laboratox-j--tuested vkUh ~a number of ion-exchange resins t
;1, Yu2j ma66,-Av-17,~M-410P 'aad vi achl ve ad
AILI-M e d equate fraction]
J, )_,Athe de ce
:purity vith a specific load of no more then I k% of the initial ion-exchange resin
imer m SU-0 2 classification ch=*er cross-section per second. A method is presented
~ior determinin& sorter dimensions. Also described Is a rapid classificatIon method.-
,for industrial use, utilizing weights, a tim-_r, and the granulo-.1--tric cuvwneof the
starting mixture. Suspended-layer hydraulic classification eliminates granule
`amnage- occurring-w:LJ,,h--;he-L--cb~mical-h=dling -of-icn-exchange resins. _0rig.__aXt.__'
.has- 4 figures P-2 equations.-.
ASSOCIAXION.t. none
WMWEDS UTE ACQ8 10 JYM 65 ENCL2, 0.2
SUB CMET ML :Mto REF SOVI 005 OTHER-.. 000
Card

vmismv,, m.s.; KOMAROVSKIYP A.A.--
Hy&oclassifier for fine grain material. Gore Shur. no.505 IV
163v (MRA 1685)
(Pro dressing-Equipmnt and supplies)

KOMAROVSKIYOkeksand Borlsovich, zhurnalis'; RABOOVICH, M.., red.
[A month in the director's chair; a business diary) Me-
siats v direktorskom kresle; delovoi dnevnik. Moskva,
I
o/ Politizdat, 1965. 86 p. kVIRA 19:1)
1. Korrespondent "Ekonomicheakoy gazety" (for Komarovskiy).

A All LEAP 9 N 0 a p 4; 0,
.4 41
tie Is 00
11tW"v tm tbr ccAut(., Vt up
0 Vlo, At to do nx agmt Ibc rnults. j,
goo
00,3
06
a ~Og
goo
see,
a
goo
4' 094
ASS.SL4 SITALLUNSKAL UffItAILAC CLA11"Olp" U60
u 111 if in It ;,
It If 10 0 of a
Mae 0 0 00-000
* Gi * 0 0 0 0 -e

Pik 2 hT 5

laflume of the ItcWtuff fit the 4110Y Aft'l tot the Pfeil.
$Ogg of a third tle"Ont on the defolmifulton of MA"40.
of" dAw of threalum In 00*18, Kf forlill
lawa. Add. 4valsh S.S.S.R., Ser.
SWOcowapicifeta. of Mrs by the title patorNin
Fe 2M74 A., and of Cr by the pair Cr 3129.7-Fe 3167.8
A.. is mt liffictild by The thefluAl tl*Atrnrnt of the it-mi. If
Annealing or quirtwhipff, Ulth wrord to the influmv
tit moddid. clematst The detism. of hin Ill wustiOw to zm. Cr.
W. Mo. V. 81. and C. The calihonation lisle, kfr of life
t6,4 intttWtks of the Mrs and Fir tints. plotted antabut -
I'se Casten. of M", Is shifted upwads. Immillorl (a lt*clf, by
V
Cr 2-7, W 4-W. MO within thew 1111lit" oll
I ints lie an the some line. A still hisber-tvitig Iltic k
so~
Itabled with NI 2-25. Cr 7-114. W 2-7. Sh) 11.4 -7, lo' A
11.2-13. .4 0.0-2. C 0.4-3%. With A% Mit, top tot 11";.
NIhavt no effect an the mlibmtkut lisle. Its low-alloy
soleeb, u: to Ni 6, Cor 6. W 4. At* 2. V I.S. A[ 2. wul Cos
0.3%. ve no laduence oil the detist. Of Nfil. The
spectroazWk dtht. of Cr is unaffected by 'A' 0.2-21.-
V 0.5-1.5. Mo 02-1 fie" , and in ltish-alk-v st"It with
cr. 'ii.'
tip to :me" 2- F1, NL In Ww-alltir tip
1.1 NI 5. %V' 4. No'l. V 1.3, -d M. do not affcvt the
(let". #of Cr. N, Thom o

'o o Ilk
-
11 W
(A

a' ' .
A
00
so
*
09
jej

-
00 4! by f4p"trowsphic A"Iyolo. (it, 1111W210
i
2
1
, 1. zar6thkava tx&jru(oHuu (FacItKy -.3
.
0 dj 15. Dec. 1949, P.
goo Dest-jil" method for the %k6yvc. IsIcludes calibration
g #3 VIIrVCj ijud typiall datA,

0.
UP
0
It

009

IALsu*GKAL.
got
IL
So
Toto*i~io-oo
00 000,
o
00

CtA
laddsom of *lrd 91400"m 0a the 40161"llmiflao of
toNlotm. a", welybdosam. nickel. chromium. manp-
Coel 6", 1 , I"a Wobhun In hadurellst4 #At!lS.
A.-Cf. Konw1o"WI. INVII. A*dd- X41'k S-3-5-R, Sep.
-M. W.-MS(IM; d. C.A. 44. U17j.-Forty-clitht
hinary allayl and 64 other brid-rcohling anil cumpirz.
AuYW steel* (mbo Collis- C. N. V. Ti. all,l Cla) were Alm-
ly"d ipectril Walking curv" fw all Anil'uts
~ r%phlettly,
'"Id a table of pairs of spectlal linet life slv~ll, ltwalll-
wen that the presence or other element, dl-plAc" the
Rmtotblwymists, In thir workinji curves WhIcher
Ila of I"IfIttlikV And pilialld to Ow 0111in'll
I'll of Ow (11,
fin". It If IN~ that If gulioble eufvft tit Ort-1111, 1110
errorl In the dda. of the eltuletits cAts be limitttl td 2 Ar, I
S. Paksner -

Journal of the Iron P-1 Steel Institut e
U cmkni'd of Hom In Mgmeamers-
D1

voi. 176 Ldwafonwa

1954
A Rumian]. Th
"
of hormt In hl
1l
b
t
m
ar
t
i
tur
l1
Klio
d
pr. -
im
erm
nn
e
a
o a
e
.
oys
g
y.
p
.
Analysis at~eolm N% om Investigated uping m
I
ectmens cover ng a wide ranp
l
le
~noj ng e
ments and boren oontents of,
or cornpoBlt
mw to 0.10%. The lines B 2400-778 and Fo 2-493-25k,
were used with photometric interpolation giving mative!
errors of 2 - 8.. Working curves, including cm for ordinary;

......
--Fv.

KONAROVSKIY, A. G. 14'1 109T60
C~O, zron~ Sptctr= GOP_ 50--,.
AnAlysis
"Determinationlof Magnesium in Cast Inns by the'
Spectrum Method," A. G. Komarovskiy,-,Cen Sci Res
Inat of Techno.1 and Mach Bldg
"Eavod. Lab" Vol XVI, No 9~, 1132-1133
Describes experiments for developing method for
spectrumdkermination of Ng In cast irons.
Quartz spectrogriph of 18P-22 type was used and
calibration curves.vere plotted for both spark
-and arc excitation source s. Accuracy of metbbd
js 2.3%,

KOMOVSKIr A Dt-kand.tekhn nauk starshiy nauchrqy sotrudnik; PROKOFIYSV9
=j~~~ktor hz.-mt:;.=j rof I otv,6rea.1 TID14MA 8*T6*-inzh*p
doktor fI;*-mtem.ziaiikq otv.reg.; REffil D.F.0 tekhn.;7J.
[Method of para.3-lel curves and a system of standiks in the
ana3,vsis of alloyed steels] Metod parallelluogo grafika i
Bistema etalonov pri analize :Legirovanzqkh stalei* Le 'ad
1952. 3-1 P. (Info=atsionno-tekhnicbeskii listok, no.71 4
(MIRA 1436)
1, Leningradskiy Dom nauebno-tekbnicheskoy propagandy. 2. Wentrall-
rqy nauchno-isolodbvatellokiy.inotitut.tekbnologii i maahinostraye-
lAya (for Nomarovokiy). 3i LenlWadekiy Dom nauchno-tekhnichaskoy
Propagandy (for Tymeneva).
(Steel alloys-Spectra)

7 -7

UPR
A, un

KCKAROVSKrr. A.G.
Rapid quantitative spectrum analysis of high-alloy 'aal and othor
alloys. I%v.AN SSSR.Ser.fis.19 no.21167-169 Kr-Ap L55. (KLU 9:1)
1. Wentrallnyy nauchno-Iseledowatellskly inatitut tekhnologil i
mashinostroyanlya.
(Tartu--Spectrum analysis--Congressem)

!~'" T - k jj & 0, 4
"Tho IrIfIllellco of Tilird Elmonta on tho Determination of "olfffii~ M,
"olbalt,- Millybdenum. Nickel, Cilloromim, l4mganese, 'Oorom'-'Aluminurn and Gol'umbitim
in fleat-Resisting, Steels" IZ Ak Nauk SSS: Ser Fiz No 5, Son/Oct 1956
U-1843

k0 /A//1/? 0 V 5
SOV/137-58-8-18130
Translation from: Referativnyy zhurnal, Metallurgiya, 1958, Nr 8, p 275 (USSR)
AUTHOR: Komarovskiy, A. G.
TITLE: Local Spectroscopic Analysis (Lokall nyy spektrall nyy analiz)
PERIODICAL': V sb.: Fiz. -khim. issled. austenitn. splavov. Moscow,
Mashgiz, 1957, pp 184-198
ABSTRACT: The. spectroscopic analysis of welding seams of complex
high-alloy steels and heat-resistant alloys was conducted with
the aid of a universal generator which permitte d o_neita.~Qbtaia
following systems: 1) High-frequency electric discharge;
2) powerful condenser spark discharge at a low voltage;
3) condenser discharge of an A-C'arc; 4) ordinary arc
charge; 5) spark discharge. With the 'aim of stabilizing the
work of the generator, Z consecutively connected dischargers
were introduced into the circuit. The local analysis was
carried out under scheme 1. The current intensity in the
primary winding of the transformer was 0. 7 amp, the size
of the gap in each discharger was 0. 6 mm, the electrode gap
was I mm, C=0.01Z3 jif , L = 0. 014 millihenry, the
Card 1/2 shunting capacity C? = 100 "pf" Upon the switching off

SOV/137-58-8-18130
Local Spectroscopic Analysis
of C2 the high-frequency discharge works through a 0. 004 - 0. 005-mm thick-
ness of metal in one min. By increasing C Z , the thickness of the layer being
worked through can be increased. The upper electrode is an electrolytic Cu
rod, ground at the point into a truncated cone with a I - 1. 5-mm diameter of
the working surface. The spectra obtained with the aid of the high-frequency
spark are distinguished by the sharpness of the lines and the absence of a
background. The powerful condenser spark discharge at a low voltage occurs
as the result of the discharging of a battery of condensers (C = 4000 ~tf ),
which were first charged through a kenotron rectifier. To limit the wandering
of the discharge over the surface of the specimen, the latter is covered with a
thin insulating, layer with an opening in it, Plastic clay, plastics (1 mm thick),
mica, shellac, and lacquer (0. Z - 0. 6 mm thick) were used as the insulating
material. The enforced localization of the condenser discharge produces a
sufficiently good reproducibility and a considerable increase in the intensity
of the discharge.
1. Seam welds-Spectrographic analysis M. N.
Card 2/2

K C) "t, /I Y
Translation from: Referativnyy zhurnal, Metallurgiya, 1958, Nr 2, p 299 (USSR)
AUTHOR: Komarovskiy, A.G.
TITLE: Rapid Spectrum Analysis of Austenitic Steels (Ekspressnyy
metod spektrallnogo analiza austenitnykh staley)
PERIODICAL: V sb.: Fiz. -khim. issled. austenitn. splavov. Moscow,
Mashgiz, 1957, pp 199-225
ABSTRACT- A system has been worked out for a rapid quantitative analysis
of high-alloy steels and high-temperature -resistant alloys rela-
tive to their content of Si, Mn, Cr, Ni, Mo, W, Ti, V, Co, Al,
B, and Nb. From the standpoint of convenience of arrangement
and concentrational susceptibility the f0ll0Win8 analytical pairs
proved best:
Si 2516 - Fe 2509 Ni 2416 Fe 2415.
Si 2507 - Fe 2499 Ni 3051 Fe 3055
Mn 2933 - Fe 2937 Ni 3414.8 Fe 3407
.Mn 2933 - Fe 2921 Mo 2775 Fe 2772
Cr 2677 - Fe 2644 Mo 2816 Fe 2829
Cr Z862.6 - Fe 2874 W 2397 - Fe 2396.7
Card 1/3 Cr 2677 - Fe 2685 W 2633 - Fe 2636

137-58-2-4390
Rr'P1d
Ti 31242 - Fe 3zz6
Ti 3371 - Fe 3407
Ti 3088 - Fe 3055
* 3102 - Fe 3076
* 3111 - Fe 3076
* 2908.8 -qe,2884
V 3185 - Fe 3180
V 3111 - Fe 3091.6
Co 2648.6 - Fe 2649.4
Co 2648.6 - Fe 2636
Co 3072 - Fe 3083.7
Al 3082 - Fe 3055
B 2496.8 - Fe2493
Nb 3094 - Fe 3o67
Nb 3130.8 - Fe
3167.9
Nb 3094 - Fe
3091.6
Nb 3130.8 - Fe
3091.6
Depending on the concentration of the various components, the analysis was
made either with an arc (DG-1) or with a spark (IG-2). Optimum operating
conditions for spark spectrometry were: T = 2 amp; U = 220 volts; one dis-,
charge per half-cycle; L ~ 0.01 microhenry; C = 0.01/Lf; gap length of auxil-
iary discharge.r,=-2,.5-3 mm. Specimens were roasted for 10-60 seconds, de-
pending on the'i~lem~ent being tested for, and the exposure time was 40-60
seconds. In the arc,test conditions were the following: I= 4.5 amp (in the
case of Al --- in the case of B, I = 6 amp); U = 220 volts; discharger gap= 0.7-
1.0 mm. The primary-circuit current in the transformer was 0.25-0.3 amp.
Roasting lasted 10 seconds; the exposure time was 20 seconds. The spectro-
graph's slit width was 1.5 graduations( 2.5 graduations when photographic
Ca rd 2/3

137-58-2-4390
Rapid ~ Sr 6truA Analys:LB of. Auntenitic St.VOI.11 (Cont--.),._
.0
photometry was used). The effect of roasting in the case of the different ele-
ments was studied. A regularity was noted in the parallel shift of the calibra-
tion curves, which were plotted with reference to the binary-alloy calibration,
curves by photometric interpolation and photographic photometry for any steel
or alloy systems. With respect to each element tested for,,all the investi-
gated steels and alloys were broken down into classes. Each class was ana-
lyzed with'- reference to one specific calibration curve. To determine a single
element in a single specimen required 9 minutes in the arc test and 10 min-
utes in the spark test. To determine each successive element in the same
specimen required one minute in the arc test, 1.5 minutes in the spark test.
M.N.
1. Suel-apectrta =$Iola
Ca rd 3/3

BOV/"125-59-16-64548
Translation from: Referativnyy zhurnal. Mashinostroyeniye, 1959, Nr 16, p .127 (USSR)
AUTH0113- Komarovskiy, A.G.
TITLE: The Microspectkal Method of _'Diveatigating, the-Compositiolt oi the ISU3~face
Layer of Metals
PFRIODICAL- Novoye v traEh. mashinoatr.; ab. 2, 1957, 99 - 30
ABSTRACTt A method is described to determine by microspeetral analysis the chemical
composition of ver7 fine surface layers of metals (of a thickness of
0.005 - 0.006 mm). A universal generator was designed mid manufactured
(the electric circuit is given) which pOrmlts to obtain different condi-
tions of electric discharge. The HP dischArge of the generator waz used
by which it was possible to attain a-depth-of burnt out cavity of 0.005 -
mm. A rod of pure electrolytic copper of 8 - 9 mm in diameter,
with a fine-pointed cone and an effective area of 1.2 mm in diameter,
served as an upper du=W electrode. The sparking time of the specimen
was 60 seconds, A iniorospeotral analysis of fine surface layers of hot
Card 1/2 cracks, which formed In ingots of heatproof alloys on irtan and nickel base

S OV/ L23-59- Y5-645 4 8
The Microspecti~al Method of Investigating the Composition,of the Surface Layer of
Metals
was carried out. Data are given on the effects of capacitance and self-induction on
the sparking depth and the liameter of the spots originated on the investigated
specimen; analytical paira of spectral lines are given and the results of the micro-
spectral analysis of the tested specimens.
E.A.I.
Card 2,/2

V
%
do
IN 0 ar
It.
lot d eaux
v2 Is
AV I Ili .
95-. of
d '131,
15 ra i j t t
0
A 01.11
21 ,
I'j-211 01
A
d
it
OR!
w Ch P% 0 Jill 10-a d-j t
szia~ j * tj: .
TO 'i
-.1 zi - x C AAj .11~ %-2 0
16hill jj~o Ole S..-. a-
. _ 1 4 0 40
_4d 0
10. 00 & .4;3 a
PIS 1 5
2 . I
lit -0 9-9
r
.4 d Miss jr.ei-a
Be!:.
1 '1 .a , - j

TILUMIN, N.I., kand.fiz.-mat.nauk; YWZHIN, P.M., inxh.,-_KOMhROVSK1T,
-" . kand.tekhn.rAuk; CHUMOTA, Te.Te.. kand.tekhn.nauk;
SEDGLIV, B.A.. Imnd.tokhn.nauk; INTIN, S.D., kand.tekhn.nauk
Physical and chemical methods for the inTentigation in the
phase analymin of alloys. [2mdy] TsNiiwaH ioo:go-io6
159. (HIM 13'-?)
(Alloy@)

24(7)* SOV/48-23-9-37/57
A UTHOR i Komaro
V!!!L
TITLE: - -rre"4~~etermination of Highly Concentrated Elements in Steels
and Alloys by Means of the Spectroscopic Method
PERIODICAL:. Izvestiya Akademii nauk SSSR. Seriya fizicheskaya, 1959,
Vol 23, Nr 9, pp 1135 - 1136 (USSR)
ABSTRACTt In the spectroscopic determination of high-percentage frac -
tions of the elements Mn,Si,Cr,Ni,Mo,W,Ti,V,Ko,Nb, and Al in
alloys a considerable influence by "third" elements is exer-
cised, which manifests itself in form of apfrallel shifting
of the calibration curve or of a slight variation of the
slope of the calibration curve in the transition from one
steel- or alloy-system to another. In the present paper the
causes, of the influence exercised by "third" elements and the
possibility of reducing or avoiding this effect are investi-
gated. The results are summarized in form of three pointst
1) The use of powerful localized low-voltage pulse-spark dis-
charges leads to a decrease of the parallel shift of the cali-
bration curve. 2) The introduction of new coordinates for
Card. 1/2 the calibration curve also leads to a decrease of the parallel

The'DOtermination of Highly Concentrated Elements in SO-1/48-23-9-37/57
S.'eels and Alloys by Means of the Spectroscopic Method
shift. 3) The material of the upper part of the lower ele6trode,
influences the spectrum intensity and the exactitude of the
analysis considerably. If the line of the lower electrode is
used as a line of reference, the influence exercised by the
"third" elements is reduced or completely prevented. There,are
4 figures.
ASSOCIATIONt Tsentrallnyy nauchno-issledovatellskiy institut tekhnologii i
mashinostroyeniya (Central Scientific Research Institute for
Technology and Machine Building)

24(7) SOV/48-23-9-56/57
AUTHOR: Komarovskiy, A. G.,,
TITLE: ion of the Composition of the
Surface Layer in the Thermo-chemical Treatment of Alloys
PERIODICAL: Izvestiya Akademii nauk SSSR. Seriya fizicheskaya, 1959,
Vol 23, Nr 9, pp 1169 - 1170 (USS11),
ABSTRACT: The present paper deals with the elaboration of a quantitative
micro-spectroscopic analysis of thin surface layers, which
were produced by thermodiffusion-saturation of austenitic
refractory steels and alloys with chromium, aluminum, and
other elements. Work was carried out by means of a quartz
spectrograph of the type ISP-22, a high-frequency discharge
being used for the production of the spectrum. The compositions
of the standards used for 'the construction
of the calibration curve are shown in table 1. Several details
of the electrical arrangement are described; a copper rod of
6 mm diameter, which was sharpened to a point and the "working
platform" of which had a diameter of 1 mm served as electrode.
As an example figures 1 and 2 show the calibration curves for
Card 1/2- the determination of chromium and aluminum in thin diffusion

The Spoctrographic Investigation of the Coi.,ipoioition SOV/46-23-9-56/5T
of the Surface Layer in thu, Therrio-chemical Treatment of Alloys
layers of the surface. The depth of the diffusion layers was
determined by means of a Lietal microscope of the type UMIM,6,
and the dependence of the layer depths of the diffusion oatu-
ration on the diffusion temperature was investigated. The re-
sults obtained by investi.aationo of the-steels of the type
E1405 and E1612, which are zhowL in table 2, show that an
increase of the diffusion temperature from 1000 to 10500C causes
a considerable increase of the depth of the diffusion layer.
Accordingly, also the chromiuna content in the diffusion layer
increases. There are 2 figures, 2 tables.and 1 Soviet reference.
ASSOCIATION: Tsentrallnyy nauchno-issledovateliskiy institut tekhnologii
i mashinostroyeniya (Central Scientific Research Institute
for Technology and Uachine-building)
Card 2/2

SUIGIENKO, K.A., kand. tekhn. nauk, red.; KOMAROVSKIY, A.G., kand,
tekhn. naukp retsonzeirt; BUISH ~ S.I., red.; FUKHLIKOVA, N.A.,
teldni. red.
.(Photoelectric methods of spectral analysis; collection of
Iarticles) Fotoelektricheskie metody spektrallnogo analiza;
sbornik statei. Moskva., Gos.nauchno-tekhn.izd-vo Oborongiz.,
1961. 95 po (spectrum analysia) (IMU 15ti)
. I
~ M

S/048/62/026/007/016/030
B104/B138
AUTHORS: Buyanov, N. V., Komarovskiy, A. G.', and Sukhenko, K. A.
TITLE: Photoelectric m3thods of spectrum analysis and their
industrial application
PERIODICAL: Akademiya nauk,SSSR. Izvestiya. Seriya fizicheskaya,-
Y. 26, no . 7, 1962, 902-906
TEXT-.* Spectral analysis in Soviet industry is carried out with
photoelectric devices produced by the American firm ARL, the Italian firm'
Optico-,'.Ulano, and the British firm Hilgor, and aloo.with-the Soviet
quantometersA~C-10 (Dris-io), ~3C-i Series production of the
10-rhannel,q1tC-31 (DFS-31) is planned to start in 1962. The DFS-10
is compared with the ARL quantometer, and found to be leis accurate.
The following must be improved in the Soviet make: the amplifying and
recording system, light source, and the stand; some of the photocel-la
must be replaced by photomultipliers. In addition', the'voltage and
frequency must be stabilized. There are I figure and 4 tables.
Card 1/1

-KcIkvII)QnA4D', gvEky'd-Ii podpolkoviiik, voyennyy shturwan pervogo klaiL3a;
gvardA mayor, voyannyy shturm,-.n pervogo klabga
The keeping of a flight attitude by an airplane unit. 14or. sb.--,r.
48 no.6:53-56 J-3 165. (MIRA' 1S;6)

Structure and physical properties of the
ice cover of the (fresh) waters, MDecow, 1952

FHASE I BOOK EXPLOIrATION
TrT
Kbmarovsk1yp.A,N&.q Doctor of TecWcal Sciencesp Professor
Zaahchitnyyc abolochki yadernykh reak.torov (ftclear Reactor Cont&iment Vessels)
Moscov, Atomizdat, 1958. 66 p. 5,65o copies printed..
Ed.: Labaznov, V.I.; Tech. Ed.: Ylazell, Ye.l.
PMUVSE: This booklet is intended for scientists and engineers designing and
constructing nuclear reactors.
COVERAC-T.: The booklet deals vith the basic aspects of the design and construction
of containment vessels for nuclear reactors. Various types of containvient shells,
materials used in their construction,, and the forces and stresses in containimt
shells are &tscussed. The booklet contalms several schematic drawings of
various t1pes of reactor contaiment shells built in the U.SA, and other
foreign crAmtries. No mathematical f6roulas we given, There are 49
references: .10 Sariet, 37 English, I French, and I German.
Card 1/3
ftelear Reactor Contaim=t'Vess'516
TAxE or. WWWTS:
The Rupose of Contai=Ont Shells and Conditions Requiring Their construction 5
ll
Types of CoAtW=ent Shells
DiWms of Relative ArrmIgMent of a Contsiment Shell and BiO1091cal 30
Shielding
Arrangmen't of the Reactor and Auxiliary Rj%diORCtjTe FAluigment With 34
Respect to the Contaiment Shell
Si2eg Of COUtaiment shells 34-
Forces Acting on a Contaimment Shell
Design, A11~3mblev and Acting Stresses in a COntaimment Shell 3T
Codes and Technical SPecificatiOng for the Design of Containment Shells 3T
Materials for Metallic ContainNeUt Shells
Card 2/3

21(l) PHASE I BOOK EX.?~_OITATION SOV/2265
Komarovskiy, Aleksandr Nikolayevich, Doctor of Technical Sciences~
Professor
StroltelInyye konstruktsii uskoriteley (structural Designs of
Accelerators) Moscow, Atomizdat, 1958. 108 P. 5,400 copies
Drinted.
E.d.t A.F. Alyablyev; Tech. Ed.:*Ye. I. Mazell.
PURPOSE: The book is intended for engineers designing acceler-
ators and for advanced students of higher schools studying
acclerator construction.
COVERAGE,: The author states that the accelerator of charged
particles is one of.the most effective instruments in modern
nuclear physics. The enormous importance of the results ob-
tained with them serves as a stimulus to wider construction
of accelerator units in scientific research institutes, lab-
oratories and schools in the USSR and abroad. The lack of
literature on planning the construction of these complex in-
Card 1/4
structural Designs of Accelerators SOV/2265
stallations prompted the author to collect, systematize and
analyze the diverse writings on the Bubject. The relatively
limited experience in designing and constructing accelerators
and the limited number of operating installations make stand-
ardization of structural elements premature. The author attem-
pts to systematize and describe most of the accelerators now
operating as well as those still under construction or in the
planning stage. There are 21 references; 2 Soviet, 16 English,
2 French, and I German.
TABLE OF CONTENTS:
From the Author 3
Choice of Site for Accelerators 5
Basic Conditions for Designing the Buildings to House Acceler-
ators 6
Card 2/4

210) PHASE I BOOKEXPLOITATION sov/1986
Komexovski3r., Aleksanclr Nikolayevich., Doctor of Technical Sciences, Rrofeasor
St~oitellnyye materialy dlya zashchity Iot izlucheniy yadernylo mattdrbv i
uskoriteley (Building Matertals for Radiation Shielding in Nuclear
'Reactor and Accelerator Installations) Moscow, Atomizdat, 1958. 123 p.
6,900 copies printed.
Ed.': A.F. Alyablyev; Tech. Ed.: Ye.I. Mazell.
PURPOSE: This book is intended for engineers engaged in designing structures for
nuclear plants and those concerned with radiation-ehielding.
COVERAGk The book conside:rs shielding and engineering properties of building ma-~
terials used for radiatidn shielding of nuclear reactors and,accelerators,
Particular attention is given to special heavy-aggregate and hydrated concretes.
In the case of ordinary concretes, cousidefttion-is--- limited to their shield-
ing proje'rties and to the conditions requii4ed for maximum density and homogeneity.
The book: compiles, systercLatizes.and, as far as possible, generalizes the results
of Soviet and foreigh investigations and construction practices in the radiation
shielding of nuclear reactors. There are six appendi-'xed'-giving-dJLts-IOU!:00$ts
Card 116
Building Materials for Radiation (Cont.) sov/1986
..and applications of concrete to buildings and shielding associated irith various
types of nuclear reactors and accelerators. There are 56 referencen, 14 of--
which are Soviet, 39 ErLgUsh, and 3 German.
TABLE OF CONTENTS:
GEORAL PROBLD(S
Cliaracter and Mpgnitude of Radiation of Nuclear Reactions and Accelerators
Units of Measurement of Radioactive Radiations an d the) Shielding
Properties of materials 5
Relationships Between the Physical and Shielding Properties of a
Substance 7
Biological Effect of Radioactive Radiations
General Requirements for Radiation-shielding Materials
SHIELDING PROPERTIES OF BUILDING MATERIALS
Ordinary Concrete 13
Card 2/6

Building Materials for Radiation (cont.) SOV11986
Special Heavy-aggregate Conefetes Based on Barite Ore
Special Heavy-aggregate,Concretes Based on,Iron and Compound Iron-
ore Fillers
Concretes With Boron Admixtures
Materib.ls for Concrete Containing an Increased Amount of Bound
Water
44
49
65
6-1
72
Reinforced-concrete Structures of Special Heavy-aggregate Concretes
Effect of Temperature and Radiation on the Concrete Shielding of
Reactors
Development o-.P' Concrete Compounds for Radiation Shielding
PARTICULAR ASPECTS OF THE PRODUCTION OF REACTOR SHIELDING
MADE OF SPECIAL HEAVY-AGGREGATR'CON
Preparation of Special Heavy-aggregate;Coneretes
Trans ortation of Special Heavy-aggregate Concretes
Card P6
]Bu.ilding Mater.Lals for Radiation (Cont.) sov/1986
Pouring
I
Shrinkage andlixpansion Joints in a,Goncrete Shield
Forms for ConcretePadiation Shields
Treatment of Concrete 'Poured inthe Construction of Radiation
Shielding
Preparation an.:1.pouring of SpecisdAeavy-aggregate Concretes in Winter
EstimAtion of Economic Factors in the -Use of special Heavy-aggregate
-Concretes-for Radiation Shielding Of Nuclear Reactors and. Accelerators
Appendixes
I. Cost per ton of metallic gravel, shot, and ores for particular
reg;Lons (with consideration of transportation factors, rubles)
II. Datajbc boron and borm containing m4terials
Cara 5/6
73
75
88
94
95
100
101
102
102
103
110
110

21(9) PHASE I BOOK EXPLOITATION sov/1652
Komarovskiy,, Aleksandr, Nikolayevich, Doctor of Technical
Sciences, Professor,
Stroitel-Inyye kohatruktaii yadernykh reaktorov (Structural
Designs of Nuclear Reactor Plants) Moscow, Atomizdat, 1958-
160 P- 5,600 coplets printed.
Ed.: G.M. Pchelintseva; Tech. Ed.: Ye. I. Mazell
PURPOSEt T his is a manual for designers of the structural
portion of nuclear reactor plants and is approved by the
USSR Ministry of Higher Education as a textbook for students
studying the.technology of nuclear reactor construction at
struotural enginee~~ing vuzes.
COVERAGE: An attempt is made to systematize and summarize
the results of experience with designing.the structural
portion of various types of nuclear reactors in the USSR and
abroad. Site selection for nuclear plants, reactor shielding
Card 1/5
Structural Designs (cont.) SOV/1652
and basic conditions for planning reactor buildings are
described. In describing the structural portion of nuclear
plants the author attempts to evaluate some of the most
successful design solutions and to present general principles
proved by experience. In the chapters devoted to the nuclear
reactor buildings are described the basic conditions for
plann:Lng and structural designing of those parts of reactor
buildings subject to special requirements connected with the
protection of personnel or of the surrounding are against
radiation, and also with conditions of decontamination* A
large section of the book is devoted to illustrations of
Soviet and non-Soviet nuclear reactors. No personalities are
mentioned. There are 135 references of which 32 are Soviet,
97 English, 4 GerTMA-, and 2 French.
TABLE OF CONTENTS:
From the Author 2
Ch. I. 3electing the'Site for Nuclear Reactors 3
Ch. II. Location of Reactors Relative to Ground Surface 4
Card 2/5

nauk; VIMIGO,
aoktor tokhn,
XOMAROV!
ria*'Vw 70IIA, LA,, red* Izd-Ya; TCMM. A.M., ~te- :red,
[organization of construction of Moscow University]. Organizat oil&
robot no, stroltalletva Molbkmikogo gosudarstvannogo univereliets
imal N.V. Lomonomova. Moskva, Go@. izd-To' lit-ry po strolt.,
arkbito I strolt. mterlalam4 1958. 327 P. (mm Inn)
(Moscow University) (Building)

i SOV/97-58-9-8/13
AU,THOR: Komarovskiy, A.N-j Doctor of Technical Sciences, Professor
TITLE: -1~n~ere e ~w FInerFeased Water Content Used for Protection
Against Radiation from Buclear Reactors (Beton s.povy-
shenbym soderzboniyem vody dlya zashchity ot 'izluchenly
yadernykh reaktorov)
FMIODICAL-. Beton i Zhelezobeton, 1958, fir 9, pp 349 - 351 (USSR)
ABSTRACT: The basic requirements of this type of concrete is to
absofo or weaken the radiation of gamma rays and also
the absorption or retardation of the flow of neutrons.
The flow of neutrons is reduced as a result of the
collision of neutrons with atoms of light substances and
partly by collision with hydrogepatoms. Concrete, to a
large extent, has the property of reducing the radiation
of both gamma and neutron Ays as it contains heavy elements
ineltiding hydrogen. To increase the protective properties
of concrete against neutron radiation, special types of
aggregates are required with increased content of bound
water. Recently, concretes have been used made from
limonite and hydrogoethite iron ores. The-ehemical
composition of some limonite ore has be6n determined by
A. Ye. Desov. Limonite ore should contain minimum ?Oro
Cardl/4 of Fe203 in the case of concrete with coarse aggregate

SOV/97-58-9-8/13
Concrete with Increased Water Content Used for Protection Against
Radiation from Nuclear Reactors
and at least 60% in the ase of fine-aggregate which
should contain at least 10116 bound water. Mix with limonite
sand has viscosity 12 - 15 times higher than mix prepared
from quartz sand. During mixing and casting of this
concrete mix, containing coarse aggregate in the form of
scrap ironI a more even distribution of the aggregate is
ensured including separation of the mix. Tests carried
out by TsNIPS with limonite concrete, subjected to
compression after twenty-eight days, gave a value of
193 kg/cm The composition of the concrete was as
follows (in kg/m3: cement 325, limonite aggregate 1'.2b5,
limonite:sand 910, water 260. Tests carried out by
H.I. Davis show strength of limonite concrPe in *
compression after 3 months to be 406 kg/cm. . Frequent use
was made of a concrete based on hydrogoethic aggrd.gate for
protection of installations of the reactor in the'atomic
power station of the Ac.Sc.USSR. This aggregate was used
to increase the quantity of bound water in concrete to give
higher protection from neutron radiation, Hydr oethie
Card2/4 concrete has the following composition (in =05:

SOV/97-58-9-8/13
Concrete with Increased Water Content Used for Protection Against
Radiation from Nuclear Reactors..
cement Mark 300-400; 552i fine aggregate 410, coarse
aggregate 1 520, water 266. Protective properties of
ordinary and limonite concrete were investigated in the
Institut atomnoy energ-Ji AN SSSR (Institute for Atomic
Energy of the Ac.Sc.USSR) by V.S. Dikarev (Ref 5). Apart
from limonite aggregate for concrete with increased
content of bound water, the following minerals are also
used: glauconite, serpentine and fine amorphous silica.
In one case, concrete based on calcined slate with 20%
water content was used for protective concrete. Tests
proved that concrete with increased content of water is
not more effective in comparison with ordinary concrete
(Ref 1).- The use of barium oxide is not suitable.
Investigations carriedout by Price, Horton and Spinnie
(Ref 8) showed that sufficient effective protection from
neutronic flow-requires not morr than 0.5% hydrogen to be
present in the concrete. P1.P. Budnikov advocates the
addition of 25 - 30% CaSO4 to Portland cement. Various
Card3/4 I

SUV/97-58-9-8/13
'Concrete with Increased Water Content Used for Protection Against
Radiation from Nuclear Reactors-
I
investigations carried out by English and American
sabatists working on the same lines are discussed and
compared.
There are 1 table and 13 references, 8 of which are
Xnglish and 5 Soviet.
Card 4/4

AUTHOR- Konarovokiy, A. N. 09-4-5-4/26
-----------
TITLE: Criticiam of the Economic Expediency of Uaina Special Heavy
Concrete as a Radiation Shield (0toenka ehononicheakoy
tooloooobraznosti pri-toneni-r- oPetnial'nykh t-azholy1ch betonov
0 - 0
zahchity ot izlucheniyl
PERIODICAL: Atorqnaya EnerCiya, 1950, Vol, 4, ITIr 5,
pp 437 _ 442 (USSR)
ABS'TPRACT: By neans of non-Rusaian data, t1do problem is invoctit;ated:
whether there is any economic justification for tba use
of special heavy concrete as a radiation shield for nuclear
reactors and accelerators. For the specific Russian conditions
also econoTaic coaputations are made which allow ustodraw t'he
following conclusions:
1) There is no economic advanta:C-o in usinG apecial heavy
concreten instead of normal concrete an a radiation ohiold
for circular accelerators.
2) B '-', t'ne use of heavy concrete for laar.--a linear acco-lerators,
the costs of construction are increased by 15 to 2orP'; if
Card 1/2 barytic concrete is used,up to 6o~u;and if concrete with

09-4-5-4/26
Criticism of the Economic Expediency of UainG Special Heavy Concrete as a
Radiation Shield
metallic additions is usedgP to 72"4).
3) ExceDtions can perhaps e justified in the followilic cases:
a) Tito reactor or accelerator is Placed in n criall room
only and space in needed for the installation of e::pori-
1;1011tal devices.
b) If the collimator long-th must be very much ohortened
for reasons of intencity.
There are 5 tables and 8 references, 1 of which in Soviet.
SUBMITTED: December 14, 1957
AVAILABLE: Library of Congress
I. Radiation-Shielding 2. Concrete-4pplicatione 3. Reactors
-Shielding 4. Accelerators-Zhieldiag
Card 2/2

AUTHOR: Komarovskiy, A. N. SOV/89-5-2-3/36
TITLE; Heating of the Structures Surrounding a Nuclear Reactor
(Nagrevaniye konstruktsiyf okruzhayushchikh yadernyy reaktor)
PERIODICAL: Atomnaya energiya, 1958, Vol. 5, Nr 2, pp. 119-123 (USSR)
ABSTRACT: A report is given on the influence exercised by the heating and
the radioactive radiation of a reactor on the concrete of the
biological shield. Experimental data on experiments carried out
in England and the USA in this direction are given. The results
concerning the mechanical properties and the moisture mutent of
the conoreteare especially discussed.
For the purpose of decreasing the load of the concrete a. themal
shield consisting of iron having a thickness of 10-15 cm is being
used more and more. Recently, additions like boric acid etc. are
used so as to be able to capture a certain number of neutrons, in
it.
According to investigations carried out by the Central Institute
AS USSR, an addition of 4,5% (of the weight of the wattr) of
boric acid leads to a noticeable slowing-down of the hardening of
Card 1/ 2 the concrete. Therefore tLis addition cannot be used for

Heating of the Constructions Surrounding a SOV/89-5-2-3/36
Nuclear Reactor
protective shields which must be of exceptional strength. Good
results were obtained by using a metal shield of 100 mm thickness,
into the interior of which paraffin and boron carbide was intro-
duced. By means of this shield It was possible to decrease the
strength of the concrete of the biological shield to 1,8 m.
For the purpose of increasing theimal stability it apparently
seems to be a useful method to cover the inner layers of the pro-
tective shield with ceramic plates, but also glass wool on a
kaolin basis in a compressed state may be used with good success.
There are I table and 10 references, 2 of which are Soviet.
SUBMITTED: April 2, 1956
Card 2/2

KOH&ROVSKIT, A.N.,.doktor tekbu. nauk.
Characteristics of building shields for nuclear reactors and
accelerators using special heavy concretes, Stroi, prom, 36 no.2:-
2-9 F 158. (MIRA 11:2)
(Shielding (Radiation)) (Concrete construction)

KMMVSKIT,'Alaksandr Nikols
imigibi.piof ': d
9ktbr3ekhn.oaukj TISMTA.
~ONDT, G.Ye., tekhn.red.
Unitial stages of,building on large construction sites] Pod-
gotovitellnys raboty na kmpnykh stroitalletvakh, Noskya. Gos.
onerg.lsd-vo, 1959. 406 p., (MIRA 12:8)
(Construction industry)

21(9) SOV/89-7-3-1/29
AUTHOR: Komarovskiyo Ao H.
TITLE: Ways Leading to Steel Economy in Reactor Construction
PERIODICAL* Atomr.aya energiya, 1959t Vol 7P Nr 39 pp 205-214 (USSR)
ABSTRACT: By analysis of reactor stations the author arrives
at the conclusion that saving of steel in reactor construction
is possible only by replacing steel construotions by suitable
concrete con'structions. The following is dealt with in detail-
1) Reactor boiler: It is shown that the use of reinforced- -=-
orate boilers is absolutely within the range of possibillty.
In this case, however, the reactor type plays an impoTtant
part. In the case of a pressure pipe reactor with graphite
moderator, for instance, much steel may be saved. It i4s, how--
ever, of importance that In this case the inner layer of oon.,
orate (thickness -50 om) is made of fireproof concrete. If,
additionally, the inside of this concrete is sealed by a t 'hin
layer of steel foilt all problems will probably be solved. The
suggeation of the Academician Bekhine of the Czechoslovak
Acadeny of Sciences to use a reinforced concrete reaot-or boiler
Card 1/3 for the first Czechoslovak Atomic Power Plant A-1 wili net.

Ways Leading to Steel Economy in Rea6tor Construction
SOV/89-7-3-1/2-9
be realized as too few experiments with such zonstructions with-
in the direct reactor radiation field have hitherto bem made.
2) Thermal shield* Heating of the shield and the herewith oon-
neoted stressing of a. concrete shield might be met by cooling
one part of the s-hield andprcvidi4g that part, which is aub-
jecte-i to particularly great stress, with especially strcng
armoring. The thin cracks forming in the conorebe do not mean
an esaential deterioration of the shielding properties of t1r.s
concrete, nor is a noticeable deterioration of the strength of
the concrete under the influence of neutron irradiation (up to
12 2
10 n/cm .seo) observed. 3) Containment. It is shown on the
basis ef tha example of the Soviet 300 Mw boiling water rea!-.`~,cr
in what way the biollogical protective sheathing may a'. the ~-ame
time s3erve as'a protection against a possible explosion (3-5 at
excess pressure) by means of the use of armored concrete. If
the --ame reactor were built into a metal sphere (2 at excess
pressure - as the volume would be greater), 2-5 times more iron.
would be neededo which would, besides, have to be of higher
quality. As, up to now, also in the USSR sufficiently accurate
.method.s have not been worked out for calculating the thermal
Card 2/3 strese in the biologioal shield - its order of magnitude is da-,

Ways Leading to Steel Economy in Reactor Construction SOV/89-7-3-1/29
termined by the armoring - many experiments will still have to
be oarr,ed out in order to solve this problem. There are
6 figu es, 3 tablesi and 17 referenaeag 6 of, which are Soviet._,...
SUBMITTED: April 4, 1959
Card 3/3

80523
115-3200 s/097/6o/ooo/05/061/016
AUTHOR: Xomarovsk!i , A.N., Doctor )f Technical Sciences, Professor
y
TITLE: Temperature Resistance of Ordinary, Special, Heavy and Hydrate
Concretes
PERIODICAL: Beton i Zhelezo-Beton, 196), No. 5, pp. 215 - 220
TEXTt Referring to tests conducted in the Atomic Center of Henford, U-SA,
and In Munich, Germany, the author draws certain conclusions as -to the specific
heat capacity and heat i2onductivity of various kinds of concrete and value of
coefficients of linear heat expansion. The Soviet Designing Institute has te-sted
various types of concrete at temperatures from 100-3000C during 5-6 hours. Re-
sults of these tests in reference to magnetite concrete and concrete made wit],
scrap steel revealed that the most reg' ant concreteBwere those made from For-t-land
0
cement. In accordance with investigations conducted by TsNIPS 2500C should not be
'exceeded in the case of ordinary concrete, while in regard to bary-tic and limonite
concretes heating should be limited to 2000C. The auth-or cites the experiment s
conducted in the USA, France and Britain. These results corroborate with tho-ze -,~f
the author and the above-named Designing Institute, but are in contradiction witn
Card 1/3

80523
9/097/60/000/05/06/016
Temperature Resistance of Ordinary, Special, Heavy and Hydrate.Concretes
the indications issued by the Institute of Concrete and Reinforced Concrete of the
ASiA (Academy of Constmotion and Architecture) of the USSR, to the effect that
when heated to 2000C ordinary limonite concrete loses 40% of its resistance, con-
crete with scrap iron ar4d ordinary'sand 11%, and concrete with limonite sand and
scrap iron 85%. The indications of the Institute of the ASiA conclude that the
utilization of barytic and limonite concretes at temperatures exceeding 500C is
prohibitive without special heat protection. - The author describes the effect of
heating concrete which results in evaporation of water in concrete, which in turn
impairs the protective properties of concrete (primarily in atomic reaotbrs)
Referring to the investigations of Davis (USA) [Ref. 51 the article gives th;
percentages of loss of water incurred by various kinds of concrete on being heated
up to 9000C which percentages vary from 2-10%. These findings correspond Ji-n general
with the values ascertained in regard to loss of weight by TsNIPS whose tests ocn-
sisted in exposing various kinds of conorete to a temperature of 1OOGC for a
duration of 1 week. Results are also given of similar experiments conducted in
the Designing Institute and abroad. Kravchenko proved that the longer the time
Card 2/3

80523
S/097/60/000/'05/06/016
Temperature Resistance of Ordinary, Speci?L:L,-Heavy and Hydrate Concretes
allowed for setting of concrete, the greater is the amount of water retained in
concrete when being heated. There are 3 tables, 6 graphs and 15 references-,
4 Soviet, 8 English, 2 German and I French,,
Card

Al, Iq 2. 0
AUTHOR:
TITLE-
S108916010081061021021
Boo6/Bo63 82303
Komarovskin A. N.
New Developments in Design and Layout of Nuclear Reactors
PERIODICAL: Atomnaya energiya, 1960, Vol. 8, No. 6, pp. 505-513
TEXT: The present paper deals with the design and layout of power
reactors with special regard to the safety factor. The advantages and
disadvantages of underg-zound and overground reactors are discussed and
various details (especially of non-Soviet reactors) are considered in
this connection. The author first discusses some details of underground
reactors with reference to the Pervaya. atomnaya elektrostantsiya (First
Atomic Power Plant) of the USSR, The advantages and disadvantages of
.underground reactors are illustrated by the reactors R-1, R-3, "Adam",
and "Eva" (Fig. 1), and details of Swedish reactors are given. In the
followingp the author describes the shielding system of several
American reactors and the biological shi.eld of a Russian experimental
power reactorp which consists of reinforced-concrete blocks
Card 1/3

Now Developments in Design and Layout S10891601008VO6
N02/021
of Nuclear Reactors. Boo6/BO63 23 3
(5-4 X 2.4 Y. 1.5 m). PiiT. 5 shows a cross-sectional view of the reactor
shaft and the concrete blocks. A single block weighs 46.5 metric tons.
Today, assemblies of superposed units of Monolith and reinforced concrete
are used extensively in the USSR (Fig. 6). The shield assemblies used in
research power reactors and in the atomic power plant of Novo-Voronezh
are usually made up of ctandardized uni-'Us of reinforced concrete. In the
following, the author di8cusaes the use of concretes of different
composition. Fig- 7 illustrates the weight and costs of various shield
concretes. It may be seen that the use of ordinary concrete is most
profitable. Moreover, the author discusses the usefulness of limonite
concrete for purposes of protection. The results of investigations of
Russian planning institutes are given, and it is shown that -the increase
in costs of reactor shielding systems, arising from the use of limonite
concrete, differs largely in the various region5 of the USSR. It ranges
from 12 (Central regions) to 132 per cent (East Siberia). It is noted
that the use of compressed dry iron ores is profitable for the
horizontal biological shield. The proton synchrotron of the OIYaI
(Joint Institute of Nucloar Research) at Dubna has such a shield which
Card 2/3 A

New Developments in Design and Layout S/089/60/008/06/02/021
of Nuclear Reactors Boo6/'BO63 82303
is made of dry compressed magnetite ores from Krivoy Rog (2.62 t/m3)
and covers an area of 500 m3 (0.9 m thick). Ore costs only half as much
as a shield of heavy concrete blocks. Finally, the author refers to
investigations carried out in the USA on the use of shielding shells,
and discusses their advantages and disadvantages. Many reactors can do
without them, such as the Beloyarsk Atomic Power Plant imeni Kurchatov,
the Voronezh Atomic Power Plant, etc. Among other things, it is said
that shielding shells sometimes increase explosion hazard in reactors.
The shielding shell of the American APPR-1 reactor (Fig. 8) is also
described in detail. There are 8 figures and 14 references: 3 Soviet and
8 US.
SUBMITTED: January 28,~1960
V

10MOVSKIT, A.N., doktor takhn.nauk, prof.
Using prestressel reinforced concrete in building nuclear
reactors. Prox.strol. 38 no.2:34-38 160., (MIRA 13:5)
(Nuclear reactors) (Prestressed concrete)

'7
d,
L 2
ACGiSSIOIN UR: AMW927
A
AUTHOR: Komarovski3r _A.~7
T lTLF, Strxicture~-adsign's- a, --.conS ue on_'of-'hov,~ aceelerat bra
Sborni
3OU11VOE. k t~vadov,, n
MY V' 'ti n
ut:roital. stiva ya e _kli-.untano Olk (Dej*rtment for the cvstruc 0
Kaf i~dva
atior
riuclecx: eki-nderihd~ ilistall
ft~:: r struqturej~ beak"
derbacti-oni ele&.ro
agne i -Pro"til-4-3m -xrotr6~
urvey: J a- 9b tri- of---. oxi ti ccelerator-
ABSNIOT i A brief" - -3 s _ngi,.:,,e ent nucleai- --partiole.. a
structures a:-A il4i~ d6616n , exa~.p lasr of - acc~elel .-~Lto~s wit-h .,
dep.ressed cixcular are listedt the Broo Iven
(USA) 30-Dev of bhe Muclear Inotituto ia ,
Grt~at Britain, the 7-3ev protron sy'_nchrotron in iutharford, USA, and the 12,5-Bov
8~nchzrotron at the ArGonne Nationa-I labocatories (UiA). Three higki-enera
P-cclelerators are.-liated with coi iplax four4a tions in the foin of separate supports
tv the-hedic, ese-Aupporbs--,~ire spanned witl*. rigid bridges (beams) on
Itaid

.~~ 0

, - m
1,

ffiwffii~~ Nam
KOFMOVSKIYI A.N doktor tekhn. naukt prof.; SHAROVA., Ye.A., red.;
tel:hn. red.
[Struetural donign of accelerators] StroltellrWe konstruktaii
uskoritelei-"lzd.x!,-, perer,. MookvOL,, Goo. izd-vo(mvyaswa
t ~ MIRA 150)
shkola," 1961* 1"13 Ps
(Particle accelerators)

I.I.; NZKRASOV, K.S.; GORWJX# S.G.:;.XCKARQFSXIY,,_A.V., daktor takhn.
fiauk# prof.0' nauclmyy red.; YUDINAv L.A.g red. izd-va; SHMTWAI N.V.#
tekhn. reC
[Vibrated brick pwie3m In bousing cgmstructi~ml Vibrokirpicbmye pans31
v'zbilishchnom stmit6llstve. Moskirap Goo. iza-vo lit-ry po stroit.9
arkhit. i stroit. liateriaiamp 1461. 138 p. (MIU 106)
(Brick housion)

PHASE I BOOK FJPLOITATION SOV/5859
Komarovskiyy Aleksandr Nikolayevich$ Doctor of Technical Sciences; Profesoor
Stroitel'stvo yadernykh ustqnovok (Construction of Nuclear Plants) Moscow,
Gosenergoizdat.1 1961. 335 p. 5500 copies Firinted.
Ed.: Yu. 1. Koryakin; Ed. of Publishing Houses L. N. Toropov; Tech. Ed*:
N. I. Borunov.
PURPOSEs This book is intended for,engineers concerned with designing,
bui-ldingj and assembling nuclear plants.
COVERAGE: Problems concerning the construction of nuclear reactors,, pa Irtiole
acceleratorsi, radiochemical laboratories,, axd structures for protection
against radioactive radiation are discussed. Numerous detailed illustratloa4
bare given. No personalities are mentioned. References accompany each part,
TABLE OF CONTENTS [Kbr!dged]::-,,
23739
41/089/61/olo/oo6/004/011
J3136/B201
AUTHORt Komarovsk~p A..N.
TITLE: --Protective linill-P,Of structure-is in radioactive inetallatiOns
PERIODICAL: At*2naya enerci)~a, Y. 10, no. 6p,196-lo 597-605
TEXTt Pro-tective 1-inIngs of I buildings .-Movilrd -to -radiatim hasu'dir hive
tte purpose of -prevezrtirg' r8illoavtiVe liqufft from -panartrtting i-n-to
buildings, of sealing off -thir -biological shieldv and of facilitating the
deactivation Of surfaces and,the removal of radioactive dust. The miateria
concerned should exhibit the follovint propertiest resistivity to Tudia-
-ti6u, -to- corro ion by liquidir,or',gassis, and- to heating. - The- sec=d=7
radiattoz i:nduced bF neabnon bomb zhould- -be weak; tiormovert the
-material -should -bar wasT -to -01w=, and- should have a sufficient much ic&l
strength., Stainless steel from 2 to 3'mm thick is utilized for lining.
floors and walleg as will as dikots containing tubings for the conveyance
of radioactive and aggreasivO liquids. Thi interior of rooms, where
liquids having a radioactivity >\5- 110 4 gram-equivalent/OM3 and being
subjected to pressures"112 atia. are handled axe likewise lined with stain-
Card 1/3

2373Y
3/0"1611010100610041011
Protective lining-s- of structuxvs B'136/B201
less steel or also with 57-40 plastic foils- Steel is also used for
ventilation systems and for the interior lining of reinforced concrete
pipeatt which then serve the sole purpose of receiving the pressure*
Since) as a consequence of ne-utrou absorption, - iroz, emits gamma 'radiation
of 7.6 Mev, it- cannot be utilized for the interior lining of -the biological
shield. 57-40 plastics are recommended instead, also because the deaati-
vation of the shield is facilitated thereby. Formerly, also ferrous
metals were utilized for this purpose, e. g., in the Varoneth and
Beloy'arBk atomic power statiorep where the reiactor room, the-gonermtor
room, and others were lined with 3-4 mm thick iron sheet. Also PVC-
and special enamel varnish arer used in installations' with low -radioacti-
vity. In plants, where radiogictive and aggressive media are handled at
temperiturea up to 400OCo lXlEI49T (1Khi8N9T) steel is used, while
X18jP2fj2T-;(Xh18N12M2T) and A18H12ft3T (WONIM3T) steels are used in case
of a highe-~- aggre-saive power-emd -temperatures over 4000C. Laxi-na-ted
plates of a tainl e as I Khi ON9T at tool on CT. - 3 - (S t. - 3) or C, T. - 10 ( at. - 10)
carbon steel are also utilized~* The welding af stainless stool is
controlled by the Go8gortekhnstdzor. The plastic material 57-40, whose
properties and stability against aggressive media are, indicated, is
Card 2/3

YY
8/08~/61/010/006/004/011
Protective linings of ErtractiLres B136/B201
either welded with h_~f vrta--iWw hented,air jet# So fart no gvnerally
appltmbrl or Trorcerdure haw . Even &irvwl ape* -f or gluirF thi a material 9 excwyt-ing
adhesive 8$ which, however, io -for use on veakly Irradi-ated sites only.
On-the-o-the-r hsud-9--*ery---thiu--j7~as-tia foils- with adhesive surf ace bare- also
ueed. : -The mechanica '1 fastening. of. plates pzd- f gils- -by pegai -and -peg-Turqivr
-has been successfully introduced in 1960. The fastirdng of plastic bands
reeled off -frorm rolls is alsp dfvvritBd -in greater d%tail, Lacquer- and
enaLuel Tarnish -ooatiugV qe ~'Lae d f pr -strlictuiss i~; which -a --tem,plyrature of
600C 'iB' Mat exceeded -and in Xhich ;udiv4c#v~t An - a b bemy t -has al so
y ~s low.
teen. made. to use pyroxylin l4oquerpl Thor -Ax~ri-qan firm Shell. Chemi-Oal has
de,veloperd a s~rnthetio- reoin .; coating bused A'~ pr*;Li~gI,,.There ar~ 4~figur~a,'. X
I table, and 2 referencess! 1.4.1ovist-bloo --.%ad 1-non Sovle-t-bloc4 The
referrer~oe- to. ther B.ttglishi.lazrgitage.~publiostion reado "as followes -Nucleonics,
18, H%* 22 11,2: (1960)
SUBMITTE~j'!' February 18, 1961
Cai-d 3/3

do.'-tor tallchn.mvill:
z-.uuon*cly of ;Aomic ra, c.ors.. :,'ol:li, -troi. 1Z ,:o.

NCKAROVSKIY. A.N._i KURTSHLT, V.S.; IAVROV, A.V.; PAVLOV, P.I.;
SHIMIEV, F.Z.
The buildings, foundations and protective installations
of an accolerator,with rigid-taming for an energy of
7.0 Gov. Prom. stroi. 41 no.2:31-34 F 163. (KM& 16:3)
(Particle accelerators-Design. and construction)

- #~O~qygy:Lqh, doktor teklin. vauk~ prof.;
19MANW-1-Y _Aj~k7~qi14E.It
GRIGORi M-3 S.T.i red.; KOKOR 1.1, L.D., red.
[Panel and large-block construction of industrial buildings
and power plants] Paneltnoo i kruprioblochnoe stroitel'Avo
promyshleruVkh i energeticheskikh cb"ektov. Moskva, Ener-
-giia, 1965. 439 P. (141RA 18:3)

vichi doktor i;ekbn. naukv'~of-;
1-12 -1, all
[Constructi of nuclear reactors] Stroiteltstvo ~ade~rrqkb
ustanovok. ke2eq ejop--..~-perer, Moskvm,, Atomizdat.. 1965.
382 p. (MIM 18 -.12)

L 26151-66
ACC NRi AN6014205 SOURCE-- 03DE: UR/9008/66/000/014/0002/0003
AUTHOR: Kom!EZ!5UL (Col~~nel general of bichnical engineering cor- Depliv.
psi
Ministeri-df Defense for Construction and Quartering of Troops)
ORG: none
TITLE: Economic reform and milV:aT constructiwprojects
SOURCE: Krasnaya zvezda, 18 Jan,66, p. 2, col. 4-7, and p. 3, col..1-4
TOPIC TAGS: construction, militisry personnel
ABSTRACT: In an interview, Colomel General Komarovskiy comented on (1) changes in -7.
-the activities of the Ministry of.Defense construction industry in connection.with the
decisions of the September Plenun of the CC, CPSU; (2) the extension of a new, system
of planning,.financing and material incentives tamilitary construction projects; (3)
the instruction of militaryconsitruction cadres in tWprinciples of economics; (4)
the performance of the military-construction indxjstry in 1965 and its plans for 1966.
SUB CODE: 15/ SIMN RATE bot ORIG FEF: 000/ OTH REF:' 000
.Ord

ACC NR: Al-16012206 Monograph UR/-
Komarovsk V, Al d J.;,,h
1 -0 __Ran -L,NiW&U&. (Doctor of Technical Sciences,
FrotessorT
Construction of nuclear power plants (Stroitellstvo yadernykh ustanovok)
2d ed., rev. and enl. Moscow, Atomizdat, 1965. 382 P. illus.,
biblio. 1800 copies printed. Textbook for students at construction
institutes and faculties.
'iTOPIC TAGSt nuclear power plant, nuclear reactor design, nuclear
reactor construction, radiation shielding, containment vessel.
reactor siding, radioactive waste disposal
PURPOSE AND COVERAGE: The problems of designing and construction of
nuclear power installations are discussed. This is a new, revised
edition of "Nuclear Installation Construction#" published in 1961.
A bibliography is provided for each chapter. It is a textbook for
students in the construction, engineering, and physice,faculties at
advanced technical schools as well as a reference book for deaLgners
and builders of nuclear Installations*
TABLE OF CONTENTSt
Foreword 3
Card 1/ 4 UDC: 621*039*53
ACC NRj AM 6 0 1-1-2 66-
Part I. The Connection datwetin Physica-Technical and Shielding
Properties of Materials
Cho 1. Radiation and Its biological effects -- 5
Ch, 2. General requirements and selection of biological shielding i
materials -- 9 z
Ch, 3. The effect of the water con'tent In concrete on Its shielding!;
properties -- 13
Part 11. Concr eta and Solid Materials Used for Biological Shielding
Cho 4. Classification of concretes used for biological shielding
and binding materials used in making
them -- 19
.Cho So The ordinary and super-heavy fillers and concretes based
on them -- 24
Ch, 6. Hydrated and boron-containing fillers and concretes based
on them -- 44
Cho 7. The effect of radiation and heating on the mechanical prop-
ettiss of colncretes and the content of water in them. Reat-
resistant concretes -- 57
Ch. 8. Designing the composition of concrete for radiation
shielding -- 77
Cho 9. Evaluation of economic expediency of using special heavy and
hydrated-concretes for the.radiation shielding of nuclear
plants 87
Card 2 / 4

MUM NKI anuvL4&vu
Ch. 24. Purpose of containmont -- 249
Ch. 25. Structural diagrams and dim*nsions of containment
vessels - 253
Ch. 26. Forces acting on the containment vassal and stresses In
their materials -- 268
Ch. 27. Containment materials and construction -- 271
Part V. Peculiarities in Accomplishing Construction and Assembly-Work
in the Building of Nuclear -Plants
Ch. 28. The work of building shielding with special concrete -- 285
Ch. 29. Characteristics of assembly work In building nuclear
reactors -- 303,
Ch, 30. Execution of,spocial coat1hg work -- 319
Ch. 31. Peculiarities of working on containment vessels -- 323
Appendices -- 335
SUB CODE; 16/ SUBM DATEs 040ct65/ ORIG REFt 086/ OTH REFt 363
Card _44

BUYANOV, N.V.; KOMAROVSKIY, A
~-;_,SUKHENKO, K.A.
Photoelectric methods of spectrum analysis and their use in
industry. Izv. AN SSSR. Ser. fiz, 26 no.7002-906 Jl 162.
(MIRA 1518)
(Spectrum analysis-Industrial applications)

KOYA.ROVsKTY 1 1. -1.
5778. Naplavka izrosher-wjkh -vysokompr-antsovtstykh krestovin. 7.7., Transz~-17orisd2t,
195-1L. 18s ill. 22sm (Vsesopiz, nauch.-issled. in-t. transport-). inform. P, f')lmo,
no. 11P.) 1.500 ekz Bespl. ns obl. avt. ne ukaz tiny - -(54-153037h) 625.151;623..791-97,+
621.791,92
SO: KPl4-7,bPPYM, 1---toPis, Voll. 1, 1955.

OBUKEIOV, k.V.; MUSHCHIVA, N.K.; ~OKAROVSKILJ~.I.; VZRINA, G.P.. takhniehe-
skly redaktar.
(Welding and bailding up,railread rails] Svarka i naplayka. shelftsba-
doroxh4kh rellsov..(Kese6w. Tsesoiusayi nanchno-iseledovatel'skil
institut sholesnodoroshnogo transports,. Trudy no.110) 1955 219 ps'
(Railroads-Ralle-Welding)

KOMAWVSKIY,j I.V., '113h*
OtOide BOZOP,trud& v prom, 7 no.205-36 1? 1639
(Geological ourveye) (MIRA 16s2)

MALYARENKO, A.V.; KO~ YO 1 FE [I.S! HV Y N', Yo.").
Use of the vOh,-52 lacquer in the Mal i no far.-tory of bent furni-
ture. Pam. i tier. rrom. no.308-~,() 16,55. (MIRA 18:9)

-----!O-MAROvSKIT.-L.V. (Tomsk)
Three-dimensional gas flows with a degenerate hodograph.
Prikl.mat.i mokh. 24 no-3:491-495 MY-Je'60. (MIRA 13:10)
(Aerodynamics)

84657
S/020/60/135/001/008/030
B006/BO56
AUTHOR: Komarovskiy, L V.
TITLE: An Exact Solution of the Equations of a Spatial Non-
stabilized Gas Flow of the Double-wave Type
. I
PERIODICAL; Doklady Akademii nauk SSSR, 1960, Vol. 135, NO-1,PP. 33-35
TEXT: The author deals with the solution of the system of equations (1):
!L + u au a + 'u4 - 0, (U a2 au4 + u !!i + XU auk 0
ax4 kaxk ax. 4 X ax kax k axk V~
J 4
J, k 1, 2, 3; where U U U derLote the projections of the velocity
it 2P
upon the coordinates x d x g a the velocity of sound, I is the
1' x2t an 3
ratio of the Specific heats, x timel summation is carried out over
4
twice occurring indices. In Refs. 1-6 waves of the first order and waves
of an order lower by one than the number of unknown quantities are inves-
t1gated; Ref- 7 dealt with an investigation of double vaves for a poten-
tial flow of a gas. Here, the double wavee.are investigated by using a
Card 1/2

84657
An Exact Solution of the Equat ions of a S/020/60/135/001/008/030
Spatial Non-stabilized Gas Flow of the B006/BO56
Double-wave Type
modification of the method given in Ref. 4, without a potential flow being
assumed. The author aimed at finding an exact solution of the equations
of the spatial non-stabilized gas flow, if the problem contains three
arbitrary functions. The way. in which this solution may be obtained is
sketched out and it is shown that in the most simple case the solution for
the potential flow in obtained. There are 7 references: 5 Soviet, 1 US, V~
and 1 Polish.
ASSOCIATION: Tomskiy gosudaretvenn;ry universitet im. V. V. Kuybysheva
-(Tomsk State University imeni V. V. Kuybyshev)
PRESENTED: June 17, 1960, by L. 1. Sedov, Academician
SUBMITTED: April 20, 1960
Card 2/2

GALtPMWp I.K.; KOMAROVSKIY. L.Ye.
Ways for improving the quality of the base of carbon paper. Bum. i der.
prom. no.2421-23 Ap-Je t63. (KRA 1722)
1. Malinskaya bumazhnaya fabrika.

NEX 1. NIKHIN, Vladimir Nikolayevi ch,- ICOMAROVSKIY, Lev 'revseZevich;
SIMAKOVA, A. V. # red.
(Manufacture of thin technical paper) Proizvodstvo tonkikh
tekhnicheskikh bumag. llosk7a, Lesnaia promyshlennost',
1965. 218 P. (I.AIRA 18:7)

NERANIKHIN, V.N.; KOKAROVSKIY, L.Ye.j YARUBOVICH, S.2., red.
(Improving the technology of the productioxi of tissue
paper] Sovershenstvovanie tekbnologii proizvodstva pa-
pirosnoi. bumagi. Moskva, TSentr. ir~-t teklin. informataii.
i ekon. iseledovanii po lcisnoi~ bumazhnoi 1, derevoobraba-
tyvaiushobei promyshl.,, 1%2. 34 p. (MIRA 17:7)

KOMAROVSKIY L.Ye.,; PRIKHODIKO, Yu.N.; SOLDATENKOj, IF.I.;
M)ZJR, V.V.; VESEWVSKAYAO T.I.0 red.
[Selecting an optimal grinding set for preparing pulp
for condenser paperl Vybox- optimallnoi raziralyvaiushchei
garnitury.pri podgotovke Bassy dlia. kondensatornoi buma-
gi. Moskva# TSentr, nauchno-issl, in-t informataii i
tekhniko-ekon, issledovanii po lee-oi, tselliulozno-
bumazhnoij derevoobrabatyvaiushchei Pronyshl. i lesnomu
khoz., 1964. 15 P. (MIRA 17:12)