SCIENTIFIC ABSTRACT MARHA, J. - MARGULOVA, T. KH.

• Document Type: CREST
• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R001032310017-3
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 100
• Document Creation Date: November 2, 2016
• Document Release Date: June 20, 2000
• Sequence Number: 17
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

MARHA, Jan, inz.
..:.
Electromagnetic and turbine flowmeter. Automatizace 7 no.9:
238-239 3 164.
1. Research Institute of Inorganic Chemistry, Usti nad Labem.

MARGVELASHVILI, O.V.
Method of calculating the speed of automibile motion by the run 6f
the road. Soob. All Gruz. SS-R 26 no.5:573-578 My 161.
(MIRA 14:8)
1. Institut mashinovedeniya AN GruzSSR, Tbilisi. Predstavleno
akademikom R.R. Dvali.
(Automabiles-Dynamics)

GBIMMIYA, K*I.;_A!KV_WA3EIjILL_W.
Method for daterniaing the size of the anxiliar7 tank for aut=Dbile
air springs. Scob.All Graz.SSR 24 no-5:571-378 H7 160* (HM 13:8)
1. Institut mashinovedenlya AN GruzBBR, Tbilisi. Predstavlr7no
almdemikom R.R.Drrali.
(Automobiles -Springs)

X4,RGVEIASHVILI, 0. V., Candidate Tech Sci (diss) -- "Investigation of the phe-
noatenon of side creep of elastic tractor wheels". Tbilisi, 1959. 15 pp
(Min Higher Educ USSR, Order of labor Red Banner Georgian Polytech Inat im
S. M. Kirov), 200 copies (KL, No 24, 1.959, 138)

M~GVELASHVILI, Nikolay Semen-ovich
~
[Forest management] (LeEf,-troist-vo. Tbil-i--i-, Gana-.1--a];
1965. 237 p. [In Georgiaal 2,

~65 0
-~JACCESSION-4A _0131~
~AT5007883 s 000OW
li a. deilaye6~ -feedback. pulse genevitor-are -described, All~-
ran-, iigs. and
le.sweration -proc
itUrai.-iii
genebator-ana :a detailed-,-. si 6~ti f-,
Lof'~theTnclcksure~7 The-4uth-ors,~~exw e- t--.
LIS Lau V"%;" aUQ - lnGel~rUPWQ _-&qperd'UJLQU
Com, 1/0,

MAPLVELANI, L.P.
Algoritm for the machine translation from Russian to Georgian.
Trudy Inst. elek., avtom. i telem. AN 14:3-9 163. (MIRA 17:10

'---NARGUS, K-Te., inzh.; GORCHARMMO. I.K.. insh.
Lowering the electric power consumption of concrete plants of
the Stalingrad Building TTust. Kekh. stroi. 17 no.10:25-17 0 160.
(KIRA 13:10)
(Stalingrad-Concrete plants) (Electric power)

MARGUS, 14.Yeo, Imbe
.paratupi for welding band saws. Deroprom, 9 no,3:22
Ap
Mr 16o. (Band saws-Welding) (MIRA 13:6)

MARGUSo TA.Te., inzho
- Yew design of water-level indicators for boilers. Bezop.
trude, v prom. 3 no.10:34 0 159. NIRA 13:2)
1. Stalingradgidrostroy.
(Liquid level indicators)

q8-58-7-!6/21
Yoving the SE-3 Excavator by Means of a 1,obile r-3-60 Electric Forer
Plant.
There are 2 tables and 1 diagram.
ASSOCIATION: Tsentralinaya nauchno-issledovatellskaya laboratoriya, Stali4pad-
gidrostroya (The Central Scientific Research Laboratory---
of the StaUngradgidrostroy)
1. Earth moving machines--Operation 2. Power plants--Applications
Card 2/2

AUTHOR: Margus, M.Ye. 98-58-7-16/21
TITLE: Moving the SE-3 Excavator by M~eans of a Mobile FES-60 Elec-
tric Power Plant (Peregon ekskavatora SE-3 pri pomoshchi
peredvizhnoy elektrostantsii PES-60)
PERIODICAL: Gidrotekhnicheskoye stroitel'stvo,1956,1.'r 7,pp 45-46(USRR)
ABSTRACT: Engineer Yu,X. Kozyarskiy and the author, on behalf of Tsan-
tral1naya nauchno-issledovatel'skaya Laboratoriya Stalirgrad-
gidroistroya (The Central Scientific Research Laboratory of the
Stalingradgidroistroy) built a unit which, coupled with the
mobile SE-3 excavator, supplied the current for the running
gear of the excavator. The unit was first built on the basis
of the mobile PES-60 electric power plant, but as its gene-
rator did not meet the prescribed requirements, another
variant was built using a ZhES-60 electric power plant, and
the whole unit was placed on metal skids. The main motor-
generator comprised a driven AK type asynchronic electro-
motor of 30 kw with a phase rotor, a direct current genera-
Card 1/2 tor of PM-290 type and an excitation-generator of 2-5 kw.

MARGUS H Y . ,,,insh.
6_0 -
If , -
Modified control board for cement-unloading machinery. Hekh.stroi.
14 no.8:25-26 Ag '57. (MIRA 10:11)
(Loading and unloading)

SHOLYAR, A.A., inshener: HARGUS. Me., inshener; GRIOCRYAN, TuA,
inzhener.
Automatization of dralnago In hydrotechnlcal construction work.
Gidr.stroi. 23 no.5:9-11 '54. (MIRA 7:8)
(Dams) (Drainage)

MAR U ~~;qyj,pm, A. , red.
[EconorAc importance of Estonian forests] Zesti micteade
rahvamajanduslikust tsusest. Tdllinn, Eesti Riiklik
Kirjastus, 1964. 311-1. (In Estonian] (MIRA 17:6)

MARGUS M - VAINET, A.; UEOUTS, K.; RAIET, S., red.; LaIET, E.v
........
tekhn. red.
(Russian-Estonian silvicultural dictionary]Metsandulik vene-
eesti sonastik. Tallinn, Eosti Riiklik Kirjastus, 1962 :1 78 p.
(MM 15. 0)
(Forests and forestry-Dictionaries)
(Russian language--Dictionaries--Estonian)

KAAR, E.; KOLLIST9 P.;LING, Kh.Clin2 ff.); M&AVARA, Va: MARGUS. Lf.;
NIL' SON yA. (Nilson, A.]; PAIOUSTO,,E.; REBANE.. K-h-.[Ri~b-ane,%);
SEPPI R.; VALK, U.; VEEWSTS, K.; SKVORTSOVA,A., red.;
TOCHISALU, E., tekhn. red.
(Forestry research in the Estonian S.S.R.] LesovodstvenrTe is-
ledovaniia. v Estonskoi SSR. Tartu, 1960. 61+ p. (14IRA 15:1)
1. Eesti NSV Teaduste akademia. Zooloogia ja botaanika instituut.
(Estonia-Forestry research)

EARGUS, M.
larch plantations and tIeIr health con~'i'icn in Estonia. p. 204.
TOILMEMM. BIOLCIUM111Z IZT'ZTM-.. SFEIIIIIA
(Eesti 'NSV Teaduste A-adeemia) Tallinn, 'stonia. -,.',o1. C-*, no. 3, 1059.
Mmithly list of 'East European Accessicns (77120 Vol. '31, n(... -1, "--n 1960.
~Jncl.

N
MARGUS, M.
Intrc-duction of nonindigenous trees in Iatvia. p. 337.
GAZ, WODA I TECHNIKA SANITARNA (StowarL7szenie Naukowo-Techniczne
Inzynierow i Technikow Sanitarnych, Ogrzownictwa i Gazownictwa)
Warszawa, Poland, Vol. 32, no. 6, June 1958.
Monthly list of East European Accession (EEAI) IL, Vol. 9, no. 2, Feb. 1960
Uncl.

KARGUSp 14.
A conference among the Baltic Republics on raising the productivity of swampy
forests. p.476
GAZI VIODA I TECHNIKA SANTTAFNA (Stowarzyszenie Naukowo-Techiczne Inzynierow i
Technikow Sanitarnynh Orgrzewnictwa, i Grownictwa) Warszawa, Poland
Vol-13, no.10, Oct. 1958
Monthly list of 'East European Accessions (EEAI) LC, Vol.9, no.2. Feb. 1960
Uncl.

M-RGUS, ',4.
Notes about forestry in Finland.
P. 374, (Sotsialistlik Pollumajandus) Vol. 12, no. -, Aug. 1951, Tallinn, Estinia
I
SO. 11-lonthly Index of East EjjjqQpean Acessions (ErUtI) Vol. 6, No. 11 November 1957

*Aec, us, N,
USSR/Forestry - Forest &ituras. K.
Abs Jour Ref Zhur - Biol., ro 21, 1953, 95853
Author Mar(,us, M.
Inst Society of Natural History AS Estorian SSR
Titlo Afforeatation of Lmids Not Suitable for ACxiculture in
the Estonion 8811.
OriG Pub Loodusuurijate Soltsi aastara=mt Eesti 11SV Teaduste
Ak,,%d. juures, Yez-he,,odnik O-va Yestestvoisl?yt. pri V1,1
EstSSR, 1955, 48, 293-311.
Abstract Probletis are emmictated which were treateO by t1he Institiz-
to of ZooloGy and Dotany AS Estonian SSR in comiectioii
with projects for broadeninG the forest area Li the w, m-
try by neans of utilizinG~ unfavorable la-ids. The coatent
of the scientific-rasearch topics planned by a Sector of
the Forest Institute are briefly characterized.
Card. 1/1

"Utilization of Agriculturally UnTiroductive 3ections of the -~outheasterp
Dart of the Estonian 311 for Afiorestation. (Proble-ils of Forest Cultivation
I
Techniques in Af forestation of Nonoroductive Fields in the Southeastern Part.
of the Mtonian. SSR)." Cand Aggr Sci, Lenin:-,~rad `orestry hn,gineerin,, Academy
imeni Kirov, Tartu, 10/53. (RZhBiol, No 1, Sero 54)
3J: Sim /,32, 29 :,;'ar 55

MMUNSFay, S.F. , ,
Basic results of scientific activities of the Academ7 of Sciences of
the White Maselax S.S.R. Ix 1955. Vastof AN BSSR Ser.biW.nav.
no.10-17 156. (Km 9:9)
1.Galouny vachomy makratar Presidyuma AN BSSR, chlen-karesReakdent
AN BSSR.
(Acadamr of &iancas of the White Russian S.S.R.)

Pmr-cztA~iski'y, 5f
Category: MR/General Division. scientific institutions A-3
Abs Jour: Referat Zh.-Biol., No 9., 10 May 1957, 34909
Author : Margunskiy, S.P.
Inst :not '~Lven
Title :The IN-3-mental Results of the Scientific Activity of the Academy
of Sciences of the Belorussian SSIR During 1954
Orig PuLb: Izv. AN BSSR2 1955, No 1p 3-13
Abstrset: The plan for scientific work was successfully fulfilled by the
Academy of Sciences of the Belorussian SSR. In the section of
biological and agricultural sciences, a solution was arrived
at on the question of the transformiation of the nature of Pol-
esye; practical measure for the increase of the productivity
of various agricultural crops on peatbog and turfy podsol soils.
A new kind of winter wheat was developed, the Golden; a more
effective feeding for pigs was worked out; a study was made of
the ~mter fowl of the Belorussian SSR and the fish of the Heman
river basin; work was completed on the fourth volume of the work
Card V2 -1-

li)c (.~ ov,~~I/"/
MMURSK . 51 - p
~4~ t: -
ViCtor7 of the October Socialist Revolution and the establiatzent
of the Soviet regime In White Rtwsia. Testat AN BSSR no.5:3-10
S-0 '54. (MMA 8:9)
1. Chlon-koresp=dent hkAdenit navuk BSSR
(White Russia,-Revolutlon, 1917-1921)

~, MARGUNOV, Ta. (Grozny7)
A millionaire. Izobr. I rate. no.8:18-19 Ag '59.
(MIRA 13: 1)
(Krishtopov, Georgii *Nikolaevich) (Groznyy--Oil reservoir engineering)

. I. . Jzhon8r,
r It MMUS. -".- --, Traat,
VVOIOY 0 If e A 4 9 iuzhens, ~_ -:~*: in stalluo Nine Building (HLRA 10:7)
egional bases 1? 157.
Fistablishing r no.z-.26-27
silal,ht .atrol. iRls)
Treat tlushajhtostrO7-b.,,djngs) m1ter
1
. (Donets Basin-Muing

STT~IKOVICH, M.A.j, 'kad-3pa-4-k; ;~ILIRGULIIGVA, T.Kh., daktor tekhn, naLA, prof.
Th e rmadl r,,, 7
r C, na r n T
Te~!,Iener~re-,ika 12
JT't 165.
1 AN SisR i ener chuskly i nstuil L'A

AKOL'ZIN, P.A.; GERASIMOV, V.V.; KASPEROVICH, A.I.; MAMRT, A.P.;
MANIKINA, N.N.1 _MARGU;Mj~,Xh.; MARTYNOVA, 0.1.;
MIROPOLISKIY, Z.L.; Prinimali uchastiye: DYATLOVA, N.M.;
BIKBMAN, B.I.; SWRINKOVICH, M.A., retsenzent; KOSTRIKIN,
YU.M., red,
(water system -f thermal electric power plants (ordinary
and atomic)] Vodnyi rezhim teplovykh elektrostsMtaii
(obychnykh i atomnykh). (By] P.A.Akollzin i dr. Moskva,
Energiia, 1965. 382 p. (HIRA 18:3)

STYRIKOVICH, M.A., akademik; MARGULOVA, T.Kh.,- doktor tekhn. nauk
Efficient water separating systom of condensate fed 140 atm.
(14 min/m2) drum boilers. Elek. sta. 36 no.2:6-8 F 165.
(MIRA 18t4)

,.y~jtGIJLC)VA, T.a., doktor tfikhno riauk~ i I
Causes of ir,on oxi-cie ciepos-,'-S Lli
1. Noskovskly oll0r9ollc!h(,-3klY III-Stitllt
I-lr,.-,2 'Ao.,ikovsko;,o rayormogo ujravlenya

MARG.ULf1TA,,-T.Kh., doktor tekhn. nauk-, STERMAN, L.S., doktor tekhn. nauk;
WAYDTJK, k., inzh. .
.Composite.atomio elentric power plants and Indices of their thermal
efficiency, Teploonargettka 11 no.60-10 Ja 164. (iffRA-1817)
1. Moskovskiy energeticheskiy institut.

MARGULOVA, T.Kh... doktor tekhn.nauki prof.
Effect of the inequality of heat flow on deposits in steam
generating pipes. Teploenergetika 11 no. 1:43-45 ja 164.
(MIRA 17:5)
1. Moskovskiy energeticheskiv institut.

Ac=imi mi: A1,057633.
effiaLency of the nuclear uaft. Tor"Al heat ccasumptdon Is calicuUted and the
electrical efaciency or tba plant SA represented graThIca.31y as a function oc
the frac+,ica of electric power generstea in the nuclear uait for varlous
paxmeters at tcth units; a3so, punt emciency is tabulated for vario" perm-
maters. Orlge' arte lum: 11
fc=ulw 4 naareav and I table*
ASSOOLAMa: Mosko"Idy ener&eticbeskly instittat (Koacov zMW InGutite)
SaMaTM: 00 D= ACQ: 34T=4 EWL: ()0
13UB CCM: NP No rw S(W: 003 M
Card 2/2

ACCMICK NR: AP4037631 8/0096/a/000/006/000T/0010
-AUMCR: Margulpy!~,_T.1h. (Doctor of technical sciences); Ster-con, Le S.
(Doetor'of-U U-isciences); Mwqduk, K. (Engineer)
.%T1rZz Combined stopic power planta and their the=1 efficiency Indices
SOUPM Teploenergatika, no. 6, IA, 7-10
TOPIC TAGS: atomic power pl=t" atomic reactor, caablne& atomic poweer *plant,
reactor efficiency, reactor ope;~tioa
ABSTFAC.,": Great interest is being sho;m in the higher eMolency of combined
etomi,c powor operating on both arganic and nuclear fua]A* The construotica
of many nev plants Is anticipated within the next decade. The the=al unit of
the combined plant ma a it possible to superheat the steam fr= the nuclear unite
Superheating of steam generated In both the thermal and nuclear units am be ao-
conplished in the convective gas conduits of the boiler unite Thus,, superheaters
Can be made of ordi=7 steels,, aad the operating coaditions, would be the seme aa
in ordinary bollerse Two the=al schemes for a acmbined pl=t an Imesented In
Which th=al and nuclear Units operate at 1) the asma pressum and 2) at dIf-
ferento pressures* In each case,, t2wre Is a considersb3a In=esse In the ther-al
C,rd 1/2

GOLUBTSOV, V.A., prof.; STYRrKOVICH, M.A., prof, MARGULOVA, T*Kb~j
doktor tekhn. nauk, prof.
Water cycle norms of thermal electric power plants. Teplooner-
getika 10 no.lOt79-81 0163 (141RA 17,-7)
1. Moskovskiy energ-,icheskiy institut. 2. Chleny-korrespon-
denty XI SSSR (for Golubtsov, Styrikovich.

MAEtGULOVA, T,,M2,, daktor takhn. nauk, prof*
--- ------ --
Problems of the development of nuclear power evgineeriag.
and their relationship with ordinaz7 thermal power engineering.
Teploenergatika 10 no.12t6-7 D 163- (MIRA 17:8)
1. Mo-skovskiy- energeticheskiy institut.

S/096/62/000/006/007/011
Steam superheat ... E194/E454
separate fossil fuel furnace raises some saturated steam and
provides all the superheat. As the nuclear unit cannot operate
without the fossil fuel unit, the latter must have 100% standby
capacity. A circuit of this type is advantageous when the
steam conditions are high, particularly as it permits the use of
standard reheat type turbines. Circuits which could be used in
nuclear power stations with super critical steam conditions are
briefly described. in supercritical conditions the difference
between the superheater tube wall temperature and steam
temperature is less and this permits certain simplifications in
design. There are 2 figures.
ASSOCIATION: Moskovskiy energeticheskiy institut
(Moscow Power Engineering Institute)
Card 2/2

MARGULOVA Tereza Khristoforovna. Prinimali uchastiye: STFZIM,, L.S.;
RASSOKBIN, N.G.; DEIMUIYEVp B.A.; HMGELtSONJP B.P.;
MIROPOLISKIY, Z.L., red.; LARIONOV, G.Ye., tekhn. red.
(Design and calculations of steam generators of atomic electric
power plants] Raschet i proektirovanie parogeneratorov atomnykh
elektrostantsii. Moskva, Gosenergoizdat.. 1962. 143 P.
(MM 15:4)
(Boilers)
6/o07/03.1
5/096/62/000/00
F,194 /F,454 Prof esscr
'tor of Technical S
T.Y,h. Do 1e, stations
14arg"lova I "C' xr power
sper"ca t at " 61 1962, 3 9 - 1j'.L ted in the
St Ito 'Wer Senera heat
loenersltixal f super
TIT tof Po - use 0 ble
PERI OD ICNI, t Tep t and the ros d b'y the Ndou Llrated
reduce end. satl arid
-tal co- ould be thas rod"ce ted
The capi tiorLS C be used to to P 'mPlica
power Sta t. rould t .,Cha,,Zer . es a
jear circu One hea t requir oviding steam
nuc eaux wit erhea . ded b)r Pr f the
rious 5t e e ovide Sup avOI sollie 0 . side the
V
a -t arra Pr -an be t then . Aucts In
circul 0t er 0 T is c tor bu r-heater 4 , ided bY burning
M and a r ca er- the reac supe, OV to
stea ve S e i In casel the also be Pr reactor
ensi irect any can the t the
e%P t rheat using tha
erhea. ve an Supe ter, here L S LCUlt
Sup tive hea . diff' il fuel
iv
C r verY
omes - expens ulty foss
bec are a ate supel dif Ell 'Inder .
ctor S one ar and the
rea -1 in a ep rate d nue le s to have t a
steam. nace ope
fue- d the fur c
f OSS3.- de saturate 'ther 'Ombinc tI am whils
tubes 3.TL c one arrangemen t
'DrOVI ted
er -Cordingly s
superheat and ar 'bed.tl3ut of satura
Sr_r3.
.tions de
'ondl. Sements are a OU
rovide the ma I
arran

MAROWVA . T.Ch. (Hargulova., T.Hh. STEMN, L.S.
Methods of increasing the efficiency of nuclear power stations with
gas-cooled reactors. Jaderna anergie 6 no*3;74-79 Ur 160o
1. Katedra jadernych elaktraren.. Moskevsky energeticky institut,
Moskva.

,-MARGULOVA, T.Kh., dcktor tekhn.nauk, prof.; STYRIKOVICH, M.A., doktor
tekhfi.nauk, prof.
Heat and power engineering as carried out in the plan of the
State Oommission for the Electrification of Russia down to the
present day. Trudy HZI no.33:41-78 160. (KRA 15:3)
1. ChIen-korrespondent AN SSSR (for Styrikovich).
(Electric power production)

An Increase in the Efficiency of Gas-cooled S/089/607()'OV/05/04/008
Power Reactors BOO/BO56
with regenerative heating) of tT,2- In conclusion, the results obtained
are briefly discussed. There are 5 figures.
SUBHITTED: September 3, 1959
k
Card 3/3

81745
An Increase in the Efficiency of Gas-cooled 5/089/60/008/0.5/04/008
Power Reactors B006/B056
of the gas and constant high pressure with an increase in feed-water
temperature; this exerts a negative influence upon efficiency. Fig. 2
shows the efficiency changes due to feed-water temperature (for one- and
two-pressure systems). Fig. 3 shows the maximum efficiency with and with-
out regenerative heating as function of the coolant temperature at the
input (at a constant output temperature = 37500 for one- and two-pres.,-
suie pycles.lt is found that regenerative heating in one-pressure systems
leads to an increase in efficiency only if the input temperature of the
coolant tT,2 is above about 1700G, which is the case for two-pressure
cycles at much lower temperatures. Besides efficiency, also the losses
due to coolant circulation increase with an increase of this temperature.
If these losses are taken into account, the maximum efficiency for the
case of feed-water regenerative heating for one- and two-pressure sy-
stems can be calculated; Fig. 4 shows the dependence of this efficiency
on coolant temperature. As may be seen herefrom, there exists an optimum
value of tT,2, which corresponds to the maximum efficiencyo Fig- 5
shows the dependence of this efficiency (in consideration of losses and
Card 2/3
Vr

s/o96/60/000/010/022/022
E194/3135
. , KorneYeva, L.V - I
AUTHORS: Ma lova T.Kh.9 &kollzin P-'k
e
and
r:~ Stress of Samples
TITLE: An Investigation of Corrosion under
of %teel lKhl8N9T attizir~sure
PERIODICALs Teploenergetika9 01960, No 10i PP 95-96
Results are given of investigations of austenitic
T FM lKhl8NqT in water media.contairling chlorine ions at
stee under static conditions
ressu'res of 200 atm, t = 364 oCi
Me concentration of chlorine ions.ranged from 100 to 1600
mg/-Litre). The specimens were inves-tigated in deoxygenated
solution after austenisation at t = 1050 oC with and without
work hardening. The tests lasted 400 hours.
ABSOGIALTION: 14oskovskJ-Y eriargaticheskiY institut
(Moscow Power Institute)
Card 1/1
B110 /o4/008
S/ogg/60/068/05
S0()6/B056
. ~mgva
st!er La
T led ?owe,
PUP r u 0,
Iacre e.the sfaciency Of P'P. 448 - 451
TITLE*- Reactors 1 C)60' 110.1. g, 11o. 5, of the
. energi-111 I at the output deals
P'tomilai- temperature paper
pF,RIOD'ICAL Tile present (m%terla
cooling gas Op timum t cir-
e in the . fjicieaG1* of the coolan
iucreas Be In .nation Corning
to an j_ncrea determ' t i.18 Con. Fig-
TF al a cussed. . h-pressuro
MT '- Pn ith the ' Lie
ctor leads connected W t ever dIs he hIg
re ems virs % jres are j.D t
al
wi ature. . three press' ressure -sure
e . tempe two I an with p two-pre,
th
.de en ,JtbL ones ,f jj.GianG1'%e 0as.1s of the heating 0
V
cu ations the erati-AS OIL the hich no regenerative
OWS t e change i'n _e in t,r output
I
sh of a dejice OP c as t tile reac falls i.11
.hold for tile teaveratiire a ssure atures
ti-OU the steam pre gut temper
circul& . curves a(i the gas ctor
system- Tne curB a r d rea alld out
.... water 00' in a ,,-,,Oole f f irted In-
the to 3750C. cycle i. the case 0
mounts

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it.s-

81380
Z/038/60/000/03/01/007
Me-~hods of Increasing the Efficiency of Nuclear Power Plants With a Gas-Cooled
Reacto,
st.ressed, however, that even at the present state of development in equipment. and
heat notentials of working media considerable Improvements In efficiency can be
ashieved if we succeed in creating such operating conditicns as will produce an aKI,
optim,wm thermal efficiency. There are 8 diagrams,
ASSOC:A-111011L, Cbair of Nuclear Power Plants of the Moscow Powe P-4-
Institute, Moscow
ca:-d 4/4

811380
Z/038/60/000/0-3/0 1/00 7
Methods of Increasing the Efficiency of Nuclear, Pawer Plants With a Gas-Cooled
Reactor
used. Figure 3 shows typical curves Indicating the changes of ultimate efficiency
In dependence on the temperature of the feed water for cycles with one and two
pressures and 1, 3, 5 and 10 regenerative heaters respectively. It can be seen
that under the conditions considered the most favorable cycle is the one with a
regenerative heating to temperatures of the feed water t of from 100 to 1100C,
and in a two-pressure cycle to a tnv of from 100 to 13008' It is possible to
establish in a similar way the parameters of the low-pressure and high-pressure
steam respectively and the temperature of the feed water, which at given values
of tpl and tp2 produce an optimum thermal efficiency, as is shown in Figure 4.
With the increasing temperature of the gas leaving the steam, generator the ef-
ficiency on the terminals of the electric generator Increases constantly,too.
With the increasing t 2 however, increase also the losses by the circulation of
the cooling gas, restwting in turn, in an impairment of the ultimate efficiency.
The relations in this respect are shown in Figures 5 and 6. It can be seen from
w1hat has been said here that the economy of nuclear power plants with gas-cooled
reac*ors can be further increased by Improving their equipment, by a gradual
t-41731*-ion i-o higher temperatures of the coolant in the primary circuit and to
. ~ -1-157-ters, by perfecting the thermal cycles, etc. It has to be

81360
Z/C)38/60/"/O 310 1/00 7
Methods of Increasing the Efficiency of Nuclear Power Plants With a Gas-Cooled
Reactor
t! UM tb
,ae pressure at tae outlet side of the turbine. It is fur -her ass ed -at the
pressure in t1he condenser Is 0.05 atm and the losses for the discharge velocity
are 5.0 kcal/kg, and that the output of '-he turbine will not dMp below the range
olf fron, 70 to 100 rto As expected, the"q l grows with the Increasing temperature
of t-he sooling gas on the Inlet side of the reactor. The electric efficiency (ef-
f1clency on tbe 'terminals of the generator), however, charges also in dependence
on the steam pressure pv chosen in the high-pressure circuit in such a manner thaT
~* each value of t2 a specific value pv corresponds,representing the highest value
of the electric efficiency. In power plants operating with conventional thermal
"es, the thermal efficlency grows proportionally to the number of regenerative
heaters and -150 the increasing temperature of the feed water. In a nuclear power
plaint of the type considered here - if the temperature of the feed water is in-
creased (at, a constant tp, and tP2 and an arbitrary pv) - the pressure of the low-
pressure steam decreases and Its quantity increase3 with respect to the unchanging
quantity of the high-pressure steam, thus affectIng the thermal efficiency. Con-
sequently, regenerative heating esn produce, under conditicns considered her'~,
bcth positive and negative effects, depending on the number of regenerative heaters
card 2/ 4

Z/038/60/000/03/01/007
0
AUTHORS- Margulova, Tfh-. and Sterman, L.S.
...........
TT=- Methods of Increasing the Efficiency of Nuclear Power Plants With a
Gas-Cooled Reactor
/I
PERIODICAL2 JadernA energie, 1960, No. 3# PP. 74 - 79
TEXT: The article analyzes the main factors influencing the efficiency of
nuclear power plants with a gas-cooled (C02) reactor, namely the pressure of the
noolant, the size of the heat-exchange area and the temperatures of the coolant
on the inlet and outlet sides of the reactor. The calculations, on which this
article is based, have been made at the Chair of Nuclear Power Plants of the Mos-
4:~ow Power Engineering Tnstitute, in collaboration with 2 Czechoslovak students,
PlALvka and V16ek, who are studying the special field of "Designing and operation
of nuClear power equipment" at the ME!. In these calculations it is assumed that
+he minijwim difference of temperatures between the cooling gas and the working
medium at its boiling point is 200C, and the superheating of the steam in super_
heaters is 300C. The pressure losses in the piping leading to the turbine and in
the regulation valve are assumed to be 5% of the initial pressure each, and the
pressure losses in the piping and fittings of the regenerative heaters are 10% of

3/081/61/000/020/055/089
B102/B147
AUTHOR:
TITLE: Applicability of diroot-flow systems for steam generators
made of austenitio stainless stools
PERIODICAL: Referativayy zhurnal. Khimiya, no. 20t 1961g 261, abstract
201167 (8b. "Korroziya reaktorn. materialov". M., Atomizdat,
19601 163 - 167)
TEXT: It is noted that direct-flow steam generators made of austenitic
stainless steels require accurate standardization of 01 in the food
water. Similar steam generators were found to be a suitable means for
producing at prosures of 80 atm and more.IAbstracter's note: Complete
translation.
Card 1/1

Corrosion of Nuclear- (Cont. SOV/5256
PART V. CORROSION OF MATERIALS FOR REACTORS 151
Margulova, T. Kh. Effect of the Thermal Schemes of Installations,
Heat -Engineering Arrangement, and Construction of Apparatus on
the Course and Character of Corrosion Processes 151
Margulova T On the Applicability of the Uniflow Principle for
I
-StFim enerators Made of Austenitic Stainless Steels
163
Tolstaya, M. A, G. N. Gradusov, and S. V. Bogatyreva. Effect of
Electropolishing on the Water Corrosion Resistance of the lXhl8N9T
Steel and of the Type 20 Carbon Steel at High Temperatures 167
Gerasimov, V. V. , A. 1. Gromova, and E. T. Shapovalov. Inventi-
--
-

Ti-i-i-n a
Stainfies-F-S-tc-F-e
tteam-Water
gating the Corrosion Resistance of
Mixture at Temperatures Above the Critical Point and at High Pres-
sure 185

Corrosion of Nuclear- (Cont.) SOV/5256
water with various compositions, factors of metal stress corrosion,
intergranular corrosion, the mechanism of corrosion cracking, and the
corrosion resistance of aluminum and zirconium alloys. Conclusions
based on test resulti are included. No personalities are mentioned.
Most of the articles are accompanied by references. Of 238 references
97 are Soviet.
TABLE OF, CONTENTS:
Foreword 3
PART 1. METHODS OF INVESTIGATING WATER
AND ELECTROCHEMICAL CORROSION AT
HIGH TEMPERATURES AND PRESSURES 5
Gulyayev, V. N.. and?. A. Akol'zin. Methods of Testing the Corro-
sion-Creep Strength. of Metals at High Pressures and Temperatukes
Card-V4

fA
U LO V
PHASE I BOOK EXPLOITATION SOV/5256
Gerasimov, Valentin Vladimirovich, ed. , Candidate of Chemical Sciences.
Korroziya reaktornykh materialov; abornik statey (Corrosion of Nuclear-
Reactor Materials, a Collection of Articles) Moscow, Atomizdat. 1960.
284 p. 3. 700 copies printed.
Ed*: A.1, Zavodchikova, Tech, Ed.: Ye.1, Ma7el',
PURPOSE: This collection of articles is intended for mechanical and
metallurgical engineers as well as for scientific research workers con-
cerned with the construction of nuclear reactors.
COVERAGE: The water corrosion of various types of stainless steel and
alloys under high pressures and temperatures is investigated from the
point of view of the use of these materials for the construction of nuclear
reactors. Attention Is given to the following: the use of oxygen for pro-
tecttng steel against corrosion, the behavior of steel in high -teniperatur e
CaLd !j8

84637
Z/038/60/000/007/001/006
A201/AO26
Some Problems of the Development of Nuclear Power Plants With Reactors Using
Water, Water-Vapor Mixture, or Stzparheated Steam as Heat Removal Media
design- featuring an arrangement comparable to that shown in Figure 4, but operat-
ing at high steam parameters. It is a complete two-loop arrangement with a
separate low-pressure steam generator whose flow-chart is shown in Figure 8.
Pressure and -temperature in the calandria and superheater tubes correspond wit-q
those of the steam at the inlet of the turbine. The steam generator does not
require shielding since only slightly active steam is used as heat -exchanging
medi:-.~m. The secondary-loop water requires but inexpensive treatment with ion
exchangers operating at temperatures at which the corrosion of austenitic stain-
'less steel parts in Cl environment is negligible and the water ne&d not be de-
mineralized, The use of austenitic steel is also greatly reduced. For this de-
sign, the steam at. the outlet of the high-pressure ti~rbine has to have a pressure
above I at-m and a moisture content not exceeding 11%. A standard VK-100 turbine
can be used in this arrangement requiring only slight modifications. - Based on
-the arrangements shown in Figures 4 and 8, a design of a friclear power plant with
turbines using supercritical steam parameters is proposed. Its flow-chart- is
shown in Figure 9. It has a two-loop arrangement with a separate low-pressure
Card 5,46

84637
Z/038/6o/ooo/oo7/ooi/oo6
A201/AO26
Some Problems of the Development of Nuclear Power, Plants With Reactors Using
Water, Water--~Vapor Mixture.. or Superheated Steam as Heat Removal Media
st-eam general~or. The principal advantage of this design is that it does not re-
quire a steam reheater. Phe t1urbines for this arrangement. have to be such "hat
the steam mois4'are at. the low-pressure ti-irbine secl--ion. rilust no,: exceed 11 - 13%,
the temperature gradient between the heat-exchanging and working media has to be
150C and the inii~ial --team pressure of the secondary loop has to be higher than
I atm. It can be seen -',-hat for nuclear power plants with reactors using either
water, wa~'.-_r-st-eam-mixture, or superbeated steam as heat -removing media a two-
loop arrangement is the most advantageous and safest design. (Translator., J.
Kory~5.~nek). Ehere are 9 figures.
ASSOCIATIONS Moi~kevsky energet~ick~ institut (Moscow Power Institirte)
Card 6,/6

84637
Z/038/60/000/OOVOO 1/006
A201/AO26
Some Problems of the Development. of Nuclear Power Plants With Reactors Using
Water, Water-Irapor Mixture, or Superheated Steam as Heat Removal Media
vides for forced circulation inside the reactor and moisture separation outside.
However, several proposals for reactors with natural circulation have been worked
out., too. - The second group with turbines using high-parameter steam also com-
prises 4 design proposals whose flow-charts are shown in Figures 5 through 8.
Of these, the design shown in FigQre 7 was prepared for a nuclear power plant
now being built in the USSR. It is a modified (incomplete) two-loop design with
a separate high-pressure steam generator. !he steam of the secondary loop is
rehea-ted in the reactor core, which permits to reduce temperature and pressure
in the calandria tube.:a. The disadvantages of this deeign are the following- 1)
The entire power plant equipment operates with radioactive steam. 2) Due to the
high pressures and temperatures, the heat-exchanger surfaces have to be made of
.austenitic stainless steel, 3) The steam generator must be shielded as radio-
active water of the primary loop is used as heat-exchanging medium. 4) The
calandria tubes of the react-or operate at a pressure substantially higher than
the working preSsure at. the turbine inlet. 5) The residue of the steam generator
is radioactive and requires SDeCial procezsing equipmeen-~. - Also feasible is a
card 4/6

84637
Z/038/60/000/007/001/006
A--301/AO26
Some Problems of the Development of Nuclear Power Plants With Reactors Using
Water, Water-Vapor Mixture, or Superheated Steam as Heat Removal Media
is dealt with more in detail describing nuclear power plant designs with turbines
using saturated steam, high-parameter steam, or supercritical-parameter steam.
In the first group, 4 designs are proposed with their flow-charts shown in Fig-
ures 1 through 4, Of these, the design shown in Figure 4 combines the advantages
of the previous three, doing away with a number of their disadvantages at the
same time. It is a boiling-water, two-loop design with the'steam-generator oper-
ating pressure only slightly above the atmospheric pressure. This feature elim-
inates the need for austenitic stainless steel in the heat exchanger and has the
additional advantage that the steam generator requires only light shielding or
none at all since only slightly radioactive steam is used as heat-exchanging
medium. The disadvantage of this design is that the main stage of the turbine
uses radioactive steam. In designing turbines for this arrangement, the follow-
in,g requirements have to be observed: the szeam moisture at the outlet of the
first turbine stage must not exceed 11 - 13%; the steam pressure at the inlet
to the second turbine stage has to be higher than 1 atm.; the temperature gradient
between the heat-exchanging and working media has to be 15 OC. The design pro-
Card 3/105

84637
Z/038/60/000/007/001/006
A201/AO26
Some Problems of the Development of Nuclear Power Plants With Reactors Using
Water, Water-Vapor Mixture, or Superheated Steam as Heat Removal Media
of 2.5 atm and a C1 concentration of 200 mg/l there was no corrosion at all, while
considerable corrosion was observed at a pressure of 200 atm and a C1 concentra-
tion of only 1 mg/l. These results demonstrate the necessity of as complete a
degasing of the feed water as possible and such a selection of a thermal design
of the power plant that the heat-exchanger surfaces made of austenitic stainless
steel be in the range of possibly lowest pressures (temperatures) for both the
heat-exchanging and working media. The problem of the replacement of austenitic
stainless steels by other steel types can be solved by the following.three ap-
proaches: 1) Introduction of such water treatment methods as would greatly re-
duce corrosion processes, especially by maintaining a sufficient alkalinity of
Ahe water. 2) Use of such steel types -that would be free of shortcomings of
austenitic steels and yet have a corrosion resistance in high-purity water only
slightly less than austenitic steels. Most promising in this respect appear to
be ferritic steels without. nickel and with a minimum chromium content of 12%.
3) Development of such thermal designs of nuclear power plants at which the cor-
rosion processes would rapidly decrease. In the following the latter approach
C ard e0

84637
2,12.0 V d4p 2111-, A 114. Z/038/60/000/007/001/006
PIC 2 .13( 0 - 1(j br'*b A201/AO26
ATJTHOR- Margulova, T.Kh.
TITLE- Some Problems of the Development of Nuclear Power PlantAlith Re-
actors Using Water, W&ter-Vapor Mixture, or Superheated Steam as
Heat Removal Media
PERIODICAL. Jadernh energie, 1960, No. 7, pp. 222 - 227
The article analyzes some design problems of nuclear power plants
with reactors using either water, water-steam mixture, or superheated steam as
heat removal media. The author presents several possible designs of such plants
with special attention paid to the possibility of replacing expensive austenitic
stainless steels by less expensive steel types for reactor building. Extensive
corrosion tests with austenitic stainless steels were conducted at the Department
of'Nuclear Power Plants of the Moscow Power Institute. The test were made In
water within a pressure range of 2.5 - 100 atm at boilin;3 temperatures for various
concentrations of chlorine and oxygen in the water. They revealed that the corro-
sion depended on the oxygen content (no corrosion was observed in the absence of
oxygen)-and still more on the pressure (temperature) of the medium. At a pressure
Card 1/6

MARGULOVA, !,.-Qh..
197 ~~
Some problems of development of nuclear rower stations with
reactors using water, water-steam mixture, or superheated.
steam as a heat removal medium. Jaderna energie 6 no.W-222-i-
227 J1.160.
1. Moskevsky energatic!7 instItut

MARGULOVA, T.Kh., dcktor tekhn.nauk
Some.problems in the development of atomic power plants with
reactors using water, water-vapor mixtures and vapor as
coolants. Teploenergetika, 7 no.10:3-5 0 160. (MIM 1-4:9)
1. Moskovskiy energeticheskiy institut.'
(Atomic power plants)

MARGIU-WV4,-I!.P,p
Efficient water operating conditions and therul, schemes of
atoole power pUnts vItb hj& pemmtere an& superheating
of the steam in the reactor. Nauch.do1rl.vyo.ohlro~7; onerg.
no-2:311-318 159. (MIRA 13:1)
1. Rekomendovana kafedroy atomnykh alektrostantsly Mostrov-
skogo energeticheakogo instituta.
(Atomic power plants)

Dsov/96-5,9-9- 5/2 -':--
The Use of Stepwise Dvaporation and Steam Scrubbing in the Itearn-
L,
raising Insballat-Jons of Atomic Power Stat-ions
case a somewhat different circuit, illustrated in Fig
may be pveferable. Here the second stage of evaporation
operates at a pTessure lower than the pressure in the
first stage of evaporation and delivers saturated steam
to the reheater. This arrangement may be cheaper, It
is considered that both stepwise e~raporation and steam
Card 515 scrubbing wita feed water should find wide application at
atomi-- power stations.
There are 4 figures and 3 Soviet references.
ASSOCIATION: Moskovsk-iy energeticheskiy institut
(Moscow Power Instit7ite)

SOV/96-59-9-5/22
The Use of Step vrise Evaporation and Steam ScrubbIna Jr, the Steam-
raising Installations of Atomic Power Stations
and it suffices to have 5% of the evaporation in the
second stage. Steam-raising in the second stage of
evaporation requires the heating surface to be heated by
a heat-translker medium at a higher pressure than in the
rest of the steam-z-aising system. This requires an
additional ciroulation I)ump, which passes water through
the reactor and over the second stage heating surfane
before being throttled down to the drum pressure, The
steam from the senond stage of the evaporation may be
delivered either to the steam -volume of the first 3tage',
as shown in Fig 2a, o4r to the water volume of the first
stage, as shown in Fig 2b. Part of the feed wateT may
be delivered to the steam-washing device of the secon-d
stage, as shown in Fig 2B~ The merits of these circuits
are discussed and it is concluded that the choi(~e vrill
depend on design considerations; the circuit of' Fig 2b
is probably the most suitable. The above discussion o-~'
water conditions in an atomic power station with super-
heat in the reactor is valid for high steam pressures.
Card 1+15 If super-high steam conditions are used with reheat, one
of the circuits of Fig 2 may still be used, but in this

SOV/96-59-9-5/22
The Use of Stepwise Evaporation and Steam Scrubbing in the Steam-
raising Installations of Atomic Power Stations
which is uneconomic. The method of stepwise evaporation
can provide a solution to this problem. Fig 2 gives
circuit diagrams of various possible methods of doing
this. The zone of the greatest concentration of
impurities and corrosion products is made the second
stage of evaporation, and the latter is located outside
the reactor. Therefore, phosphates can safely be intro-
duced in the water to convert scale-forming salts into
sludge, which can be removed by blow-down at the rate of
0.3 - 0.5%. The concentration of impurities in the
second stage of evaporation, or in the installation as a
whole in the absence of stepwise evaporation, can be
expressed as a proportion of meir concentration in the
feed water. The ratio is given by Eq (1), and the
corresponding ratio when stepwise evaporation is used is
given by Eq (2). Fig 3 shows curves of the concentration
of blow ... down water as a function of the amount of !3team
raised in the second stage of evaporation for two
different amounts of blow-down. Evidently there is no
Card 3/5 need to increase the overall blow-down rate above 0.5%

SOV196-59-9-~122
The Use of Stepwise Evaporation and Steam Scrubbing in the Steam-
raising Installations of Atomic Power Stations
directly into the reactor; various possible
ways of
introducing the water are shown in Fig 1. Their merits
are discussed and the circuit of Fig 1B is recommended
b.eowase it permits of improved de-aeration of the feed
water and de-act-iiation of the steam. Acc-ordingly the
rest of the article Is concerned exclusively with this
circuit. Ordinary power station practice shows that there
is always some leakage at the rolled ("expant.3-ed")
condenser-tube joints,so that small amounts of cooling
water leak into the condenser. This means that Compounds
of calcium and magnesium. and also corrosion produots of
brass and steel, can find their way into the condensate.
In a single-circuit power station these impurities would
reach the reactor. By using suitable steam purification
inside the boiler the deposits may be removed from the
boiler in the form of sludge rather than from the react*or
in tlie form of scale. Water conditions In the reactor
should be such as to prevent the formation there of scale
or other deposits. With the usual rates of cooling-water
Card 2/5 contamination of condensateg deposit formation in the
reactor could be prevented only by having 3% blow-down,

sov/96-59-9-5/22
AUTHOR: Margulova, T.Kh (Doctor of Technical Sciences)
TITLE: __Y_he'Ts"~_~Tf St-dVViise Evaporation and Steam Scrubbing in the
Steam-raising Installations of Atomic Power Stations
PERIODICAL: Teploenergetika, 1959, Nr 9, pp 27-31 (USSR)
0
ABSTRACT: The method of stepwise evaporation which is widely used
in ordinary power engineering to ensure purity of the
steam can also be successfully applied in atomic power
engineering, with certain modifications. In atomic power
engineering the main object of stepwise evaporation is to
reduce the contamination of the reactor water by
dissolved impurities, especially corrosion products. This
ensures freedom from deposits on the heating surfaces and
reliable operation of the reactor. In addition, stepwise
evaporation will permit reduction of the output of
evaporative or other devices for treating reactor blow-down
water and may in certain cases make possible the use of
carbon steel in place of stainless steel. In atomic power
stations with high steam pressure and super-heating in the
reactor the use of a two-circuit construction complicates
Card 1/5 the installation. It would be very desirable to use a
single circuit arrangement delivering the feed water

t
WIRGULOVA T.Gh. [2-fargulova, T.Kh.]; MEDONOS, S. [translator]
It 2
Education of experts in the peaceful use of mclear
energy. Jadernq energie 4 no.8:210-215 Ag 158.

SOV-3-58-10-13/23
AUTHOR: Margul ova T Kh., Professor, Doctor of Technical Sciences
TITLE- The Prospects of a Laboratory for Solving Special Problems
(0 perspektivakh odnoy problemnoy laboratorii)
PERIODICALi Vestnik vysshey shkoly, 1956, Nr 10, pp 69 - 70 (USSR)
ABSTRACT: On 20 March 1957, a thermo-physical laboratory for solving
special problems was organized at the Moskovskiy energeti-
cheskiy institut (Moscow Power Engineering Institute). The
author gives a brief review on its activities. She states
the problems that were to be solved by the laboratory, the
difficulties encountered, and points out that the works
carried out have made the laboratory a leading organization
in examining problems of modern power engineering. In the
near future the the7es and the volume of reseprch will ex-
pand. She suggests that the Ministry convene a conference
of supervisors of such laboratories for an exchange of ex-
periences and opinion.
ASSOCIATION: Moskovskiy energeticheskiy institut (Moscow Power Engineering
Institute)
Card 1/1

MARGUWVA, T.Kh.
Water-s"tem problems of steam generators in atomic power plant-a.
Nauch. dokl. vys. shkoly; energ. no.l-.189-195 158.
(MIRA 11:10)
l.Rokomandovano kafedroy- atomnykh elaktrostantaiw Moskovskogo
onergatichaskogo instituta.
(Atomic power plants)

MARZULOVA, T.Mi.,prof., red.; WILORAYN. E.E..red.; VOROUIN. K.P.. tekhn.red.
(Problems of corrosion nnd heat exchange in liquid metalse Translation
from American and British aonrces] Nekotor7e vo-prosy korrozii i
teploobmena v zhidkikh metallakh. Hosiva. Gas. energ.izd-vo, 1958.
39 P. (MIRA 11:9)
Morroaion and anticorrosives)
(Heat--Transmission)
(Liquid metals)

The rational orgam-igation ot wctsx im SOV/96--58-12-4/18
single-circuit atomi~-~ pqrs-- st&tfi--v v--~th botltrzj-vate-~
gemerator, tvA this im not rsgard6d as a 4*sadvaxt&g4,.
ThOs &r4 I fig-i~ros; 3
AS80CUTIOMs Vowpow ~ow4E 41,Vrfpk-GTek:-,y Energe-wicheakiy InstAt-&-t.)
Card 3/3

The rational organisation of water ^.Ouditlons in siDgle-1,irtuit SOV/96-58-12-4//18
atomio power stations with boiling-water rea,tors,
pressures, tbfra will bs -to transfer of water fren the second stage
to the first. As both Ist3 of blow-down water are aztive, they are
both dire-r-tsd to a sing2s o-faporallive lnstallat!on~ Ths iorrsepoading
eircrit is asen tn flg.l~, Two other possible -,irv~Jts are ia~,Lxded
in Fig.!~ Calaulatjkons ~,een made to -ompa-re the g,-Veu in
Fig.1; ths main reev-Its c.-e, sst out in Tabl6s.,L, - 3. and graphed
an Figs.2. - 7. Kib sa~eh xasa V-.s output of the evaporativ+ equipment
is assumsd ;onat&w", also th* th~srmal output of the reactor and steam
generator. Ths varioue zizz.-aiia are then -lompared and it is first
ahowm that the zir,~xUl; ~,f 1714.1t. with parallal blow-down is the
least faTovrall%. E~y usirg the cir,-~zit of Fig-It. tts tonneetration
of malt and aorroaior. prodv.4tq An thi reaetive water is ouly 2.3
times that AD 'thS te8d W&t4X; thus it is S* timss nore pure than when
the ttxcm--ft, of Pig lt~ Aa ~iasd. The use of slvepwAse evaporation in
a atovit 1poy6r station with boiling-watsr rea,,,tors is
only possible if tht stattom iiirvmit ft5liAss the separate &team
~a-j 2/3

V
AUTHORS: Glazunov, A.A. and Margulova, T.Kh-, Professors 3-9-30/31
TITLE: Dean's Dities (0b obyazannostyakh dekana)
PERIODICAL: Vestnik Vysehey Shkoly, 1957, # 9, pp 92 - 93 (USSR)
ABSTRACTz The obligations of a Dean are manifold. He conducts the
scientific educational and methodical operations of the chairs
and the faculty, solves crucial problems of faculty life, con-
ducts the educational training, etc. For this task persons must
be appointed who have the necessary methbdical and pedagogical
qualifications. The authors mention the various obligations
of the Dean, such as the control of lecture courses, exercises,
laboratory work and course projects, all of which have to
correspond with the faculty outline. The Dean has also to
supervise the equipment of laboratories, the supply of handbooks
and appliances. The authors suggest the convening of an All-
Union Methodical Conference of Deans to be followed up by bi-
annual conferences.
ASSOCIATIONt The Moskva Institute of Energetics (Moskovskiy energeticheskiy
institut)
AVAILABLE: Library of Congress
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MARGULOVA. T.Kh., doktor takhn.nauk, prof.
, ,,
Advanced education in power engineering during the last 40 7ears in
the U.S.S.R. Teploenergetika 4 no.11:40-45 H '57. (MIRA 10:10)
1.Hoskovskiy energetichaskiy institut.
(Technical education)
(Electric engineering)

MMUWVA, -.,,4,pktor takhnic.heskikh nank.
Methods of ingwing steam purity in high azd cuperbigh pressure
Installations under construetion. Xnergetik 5 no-3:12 Kr '57&
(Boilers) (HLRA 10:3)

Konfederatov, I.Ya., Doctor of Technical Sciences;.Mar Llova T.Kh., Doctor of
Technical Sciences; Meshkov, V.V., Doctor of Technical Science`s;,troV9vG,N'.-,
Dodtor of Technical Sciences; Si-rotinskiy, L.I., Doctor of Technical Sciences;
Styrikovich, M.A., Corresponding Member, U56h Academy of Sciences; and Shney--erg,
Ya.A., Candidate of Technical Sciences. Ed.: Matveyev, G.A., Doctor of Techni-
cal Sciences; Technical Ed..- Nedvedev, L.Ya.
PbRFOSE: The book is intended for technicians in all branches of heat engineering.
COVERAGE: This book presents the development of the basic branches of heat engineering
in the Soviet Union and.it is the first volume of 3 volumes entitled History of
Power Technology in the USSR. The first chapter gives a concise history of the
development of heat engineering from its very beginning to the middle of the 19th
Century when the fundamentals of the theoretical heat engineering were established.
A detailed description of the development of heat engineeriiig in pre-Revolutionary
Russia is given in Ch. 2 to 5 and its status before 1917 is described. In the min
part of the volume, Ch. 6 to 16, the development of various branches of the Soviet
neat engineering is presented. The theoretical fundamentals of heat engineering,
of manufacturing boilers, turbine installations of heat power plants, district
heating, heat control, automation of thermal processes, and cooling tech-dques are
covered extensively. Each chapter is supplemented with a bibliography. -he boolt
is illustrated with photographs, charts and diagrams, worked out by the authors of
the respective chapters. At the end of the book there is a chronological list of
significant events in the development of heat engineering.

MAXIULOV 'A T Kh. (Doctor of Tecnical Scie.--,ces)
Moscow. Energeticheskiy institut
Istoriya energeticheskoy tekhniki SSSR v trekh tomakh. t. 1: Teplotekhnika
(History of Pover Engineering ifi the USSR in Three i(lumes. v. 1, Heat Eng-ineering)
Moscow, Gosenergoizdat, 1957. 479 P. 5,000 copies printed.
Ed.-Compiler: Konfederatov, I.Ya., Dcotor of Technical Sciences; Authors: Badyllkes,
I.S., Dcotor of Technical Sciences; Belindkiy, S.Ya., Candidate of Technical
Sciences; Gimmellfarb, M.L., Candidate of Technical Sciences; Kalafate, D.D.,
Candidate of Technical Sciences; Kertselli'!O- L.I., Professor; Kovalev, A.P., Doctor
of Technical Sciences; Konfederatov, I.Ya., Doctor of Technical Sciences; Lavrov,
V.N., Doctor of Technical Sciences; Lebedev, P.D., Doctor of Technical Scienceo;
Luldriskiy, V.V., Doctor -f Technical Sciences (dei-eased); Petukhov, B.S., Doctor
of Technical Sciences; Satanovskiy, A.Ye., Doctor of Technical Sciences; Semenenko,
N.A., Doctor of Technical Sciences; Smellnitskiy, S.G., Candidate of Technical
Sciences; Sokolov, Ye.Ya., Doctor of Technical Sciences; Chistyakov, S.F., Candidate of
Technical Sciences, and Shcheglyayev, A.V., Corresponding Member, USSH Academ.,,. of
Sciences; Editorial Board of set: Bell kind, L.D., Doctor of Technical Sciences;
U'lazanov, Doctor of Technical Sciences; Golubtsova, V.A., Doctor of Technical
Sciences; Zolotarev, T.L., Doctor of Technical Sciences; Izbash, S.V., Doctor of
Technical Sciences; Kirillin, V.A., Corresponding Member, USSR Academy of Sciences;

MA--RG,LiLU\/I) T-16i.
GOLUBTSOVA, VA.9CHILIKIN, M.G.; MAROWTA, T.Kh.; HESHKOV. T.V.;
DWZDOV, N.G.; PEREMIN, M.A.: SM12MY. W.A.
Professor V.S. Pantiushin. glaktriebestvo no.7:93 J1156. (KMA 9:10)
(Pafttiuahln. Tasilit Sargeavicb, 1906-)

. BADYLIUS, I.S.---(continuad) Card 2.
Vol. 1. [Heat engineering] Teplotekhnika. Avtorskii kollektiv toma
BadylIkes i dr. Red. -soot. toma LIA.Xaafedoratov. 1957. 479 P.
(KIRA 10:8)
1. Chlon-korrespondent Akademii nauk SSSR (for Shchaglvayev,
Kirillin, Sty-rikovich). 2. Moscow. Moskovskiy energeticheskiy
inatitut
(Heat engineering-Histor7)

BADYLIKRS, I.S., doktor tokhatchaskikh nauk; BELINSKIY, S.Ya.. kandidat
takhaicheakikh na uk; 'GIMCLI FARB, H.L., k9adidat takhaichaskikh
nauk; KALAVATI. D.D.. kandidat takhnichaskikh nauk; MTSELLI, L.I.,
professor; KOVALCV, A.P., doktor tekhnichaskikh nauk; KOMMIRATOT.
I.YA., daktor takhaicheskikh nauk; IAVROV, V.N., doktor takhniche-
skikh nauk; LXBEDZV, F.D., doktor tekhnichaskikh aauk; LUKNITSKIY,
V.V., doktor takhnichaskikh nauk [deceased]; P%TUKHGV, B.S.. doktor
tekhnicheakikh nauk; SATANOVSKIY, A.Ye., keadidat tekhaicheakikh nauk;
SEHERMO, N.A.,daktor tekhnicheakikh nauk; SHELINITSKIY, S.G..
kandidat takhnichaskikh nauk: SOKOLOV, Ye.Ya., doktor takhaichaskikh
nauk; CHISTYAKOV, S..*., kandidat tekhnichask-ikh nauk; SHCHIGLYAYEV,
A.T.; BILIKIND. L.D., doktor tekhnichaskikh nauk, redaktor,- GLAZUNOV,
A.A., doktor tekhaicheakikh nauk, redaktor; GOLUBTSOVA, V.A., doktor
tekh~icheskikh nauk, radaktor'; ZOLOTAREV, T.L.. doktor tekhnichookikh
nauk. redaktor; IZBASH, S.V.,.doktor takhaichaskikh nauk. redaktor;
KIRILLIN, V.A., redaktor UL~0VAT&Qh..,. doktor tekhaichaskikh
dio tor
nauk, radaktor; MESHKOV, V~.V...UN tot e nichaskikh nauk, radaktor-,
PETROV, G.N...doktor tekhniehaskikh nauk, redaktor; SIRGTINSKIY, L.I.,
doktor tekhnichaskikh nauk, redaktor; STYaIKOVICH, H.A.. redaktor;
SELOYBERG, Ya.A., kandidat takhnicheakikh nauk, redqktor; MATVRYEV.
G.A.t doktor tekhnichaskikh nauk, redaktor; KOVEI)EV. L.Ya.,
takhnichaskly redaktor
[History of power engineering in the U.S.S.R.; in three volumes]
Istoriia energatichaskoy takhniki SSSR; v trekh tomakh. Moskva,
Gas.energ.izd-vo.
(Coatinmsd on aext card)

j~W~~ -q leraza, Khrisoforovna; KROLODOVSKIT, G.Te.. redaktor; TOROUIN, X.P.0
W
, _~ , v,
takhnichaskiy redaktor
Dayout and thermal calculations for boiler installations] KoVonovkel
i teplovoi raschat kotloagregata. Koskva, Gos. energ. izd-vo 1956.
(HIRA
9:12)
120 Pe
(Boilers)

MARGULOVA, T.Kh.p daktor tekhn.nauk; GRADSKAYA, L.V.., inzh.; XMIAN, E,Ya., inzh.
Intake of cooling water in condensers* Elek.sta. 32 no-4:36-40
Ap 161. (Condensers (Steaii~)--Cooltngll (KMA .14:7)

MARGUIPTA, T,,Kh.. doktor tekhnichookik-h nauk, professor.
~--
Conversion of Loeffler boilers for evaporation In stages.TrudF MM
.no-25:133-143 '55- (Boilers) (HWA 9:1)

'11,14 kf- C/ V'4
AID P - 2881
Subject USSR/Engineering
Card 1/1 Pub. llo-a - 14/16
Authors IMPlargulova, T. Kh., Doe. Tech. Sci., Prof., Katkovskaya,
h. ~Fch. Sci. , and Borodulina, L. P.
Title Nomograms for steam purity calculation
Periodical Teploenergetika, 10, 60-61, 0 1955
Abstract : The method of computing nomograms for calculating
steam is explained. These nomograms compute the
purity of steam for 2-stage evaporation and salt
content. Three diagrams.
Institution : None
Submitted No date

~r, kh.
Subject USSR/Engineering
Card 1/1 Pub. 110-a - 3/16
AID P - 1826
Author : Margulova, T. Kh., Doe. of Tech. Sci., Prof., Moscow
Title : Determination of feed-water conditioning in
relation to the purity of steam
Periodical : Teploenergetika, 3, 14-17, Mr 1955
Abstract : The author presents a method of calculation of
steam purity for various systems of the feed-water
loop of drum boilers. A calculating nomogram is also
presented. The author demonstrates that substantiated
magnitudes of basic feed-water characteristics can be
selected only on the basis of steam purity calculations.
This, in turn, is determined in practice for once-
through boilers only by the purity of the feeding
condensate. Thtee diagrams
Institution: Moscow Power Engineering Institute
Submitted : No date

KARGUL40TA. Teresa Khristoforoym; KOSTRIKIN, Yu.M., radaktor; SKVOEMSOY.
.W
Mekly radaLctor.
[Methods of obtaining pure steam] Hatody poluchentia chistogo
para. Mook7a, Qos.en6rgetlchsskosTzd-vo, 1955. 179 p.(WaA 8:12)
(Steam)

USSR/Engineering Thermotechnics
FD - 1583
Card 1/1 Pub. 41-4/18
Author Margulov, T. Kh., Moscow
Title Experience in use of radioactive isotopes for investigating vapor
purity in a semi-industrial boiler at high pressures
Periodical Izv. AN SSSR. Otd. tekh. nauk 8, 29-36, Aug 1954
Abstract Investigates radioactive isotope method for determining purity of
vapor in a send-industrial boiler at the Moscow Power Engineering
Institute, 1950-52. The productivity of the boiler was up to 2-5
tons per hour at pressures from 110 to 185 atm- Isotopes of P and
S were used for determining moisture content of the vapor, the
moisture content being determined by the ratio of the activity of
samples of the condensate of the vapor and boiler water. Determina-
tions obtained by the radioactive isotope method were then compared
with determinations of vapor purity obtained by the usual analytical
methods. Graphs.
Institution
Submitted September 24, 1954

g # /f jW&M/- 0
OV, V.A.,
nicheskikb
'A
professor; MRaM.M. T.Kh., professor, daktor takh-
nauk. ~'
Applying gradual evaporation in feeding a boiler with condansate.
Trudy KCI no.11:109-134 153. 7:11)
(Feed water)

RARGIMOVA. T.Kh., professor, doktor tekhaicheskikh nauk.
'-~
Txperimeatal examination of the relative speed of steam bubbling
through a layer of water under very high pressure. Trudy MCI no.11:
70-81 '53. WaA 7:11)
(Steam, High-pressure)

NMUWVAq T. Kb.
Subj.ect USSR/Engineering AID - P-72
Card
Authors : Styrikovich, M. A., Corresp. Memb. Ac. of Sci., USSR,
Patsukov, N. G., Dr. Eng. Sci. and Margulova, T. Kh,,
Dr. Eng. Sci.
Title : The Use of H-Na-Cationic Installations on High Preasu-re
Heat and Electric Power Plants
Periodical Izv. V.T'I., v. 21, iur3, 4-7, Mr 1952
Abstract The purification of feed water in high pressure boiler
is discussed. The lowering of concentration of slllcic
acid by partial water blowing, by washing of steam and
by stepped evaporation are analysed. The use of a H-Na-
cationic Installation is specified for different con-
ditions.
Institutions: Moscow Inst. of Power Engineering im. Molotov (MEI)
and Central Scientific Research Inst. for Boilers and
Turbines Im. I. I. Polzunov (TsKTI)
Submitted September 27, 1951