SCIENTIFIC ABSTRACT ZAJIC, V. - ZAJIC, V.

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• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R001963430008-7
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 61
• Document Creation Date: November 2, 2016
• Document Release Date: March 15, 2001
• Sequence Number: 8
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

zajict V.
-Types, of __ effective. high-voltage and ultra *&-voltage cirouit breakordi. p. 2040
Vol. 43, no. 4. Apr. 1954.
BLEKTROTF,CHNICKY OBZCR
SO: Monthly List of East Euro peon Accession, (EFAL), LC, Vol. 4, No'o- 9,
-Sept. 1955, Unal.

ZAJICIV.
Experimental laboratory for high-tension currents., the department for Shorted circuits
in Bechovice. p.108. (Nova Tochnika, Vol.2, no.h, Apr. 1957) Praha
SO: Yonthly List of Ea--t European Accession (EEAL) LC, Vol.6, no-7, Judy 1957. U'ncl.

,:IAJTCI J.
_- Technological evaluation of potatoes used for manufact*,,rin,~ in the potato industry. p.126.
..(Prurysl Potravin. Praha. Vol. 8) no# 3, 1957.)
SO: Monthly List of East European Accessions (EEAL) Ik*,.p Vol. 6p no. 7., July 1957. Uncl.

ZAJIC.. V.
High-voltage coati-actors for heavy :LnduBtrjAl application.
P. 353 (ELEUROM1111U) Vol. 12, no. 11, Nov. 1957,,
Praha, Cwhoolovakia
SO: Monthly Index of East European Accessions (EEAI) Iz, Vol. 7, No. 3,
March 1958

6
7AY% I /C0)/00 1/003/005
Am/A126
a? A / ~22 0
A1YT'iOR: ZQ1c, Vladimir
- -----------
TITLE: The influence of the surface temperature increase of a fuel ele-
ment on the efficiency of the thermal cycle of it nuclear power
plant
PERIODICAL: Jadernh energie, no. 1, ig6i, 10 - 12
TM: The article is a discussion contribution to several papers which
were preNiously published in this Journal. The author contributes some more.ac-
avrate data and points out some other factors which'may influence 'Aie thermal-
cyole efficiency 9f a nuclear power plant. V. Rkpar (Ref. 1: Vkznain z4seni pov-
rchov6 teploty palivotbho 61hnku. Jadernh on-rgie 6, (1960), '. 3
e c , str. 100, Ref.
2: Korozni problematika energetickkch reakton9i chlazenkch kysl1'CnV,.cem uhli'citym.
jadernh energie 6 (1960), 6. 6, str. 192) dealt with the potentiallties of in-
creased fuel-elem6nt surface temperature in improving the thermal-cycle efficiency
of nuclear power plants. His conclusions, however, might be Interpreted to the
effect that a comparatively slight increase of 500C in the fuol-element surface
temperature can lead to a relative increase nf 30% of the thermal efficiency of
Card 1/3

22362
Z/038/61/000/001/003/005
The influence of the surface temperature A201/A126 -
the working cycle, which is not true. For an initial steam temperature of 6T30K
(-4000C), which is provided in the design of' the first Czechoslovak nuclear power
plant, an increase of 500U would produce-even in case of an optinram Carnot cycle -
a relative efficiency increase of 5.6% only. An increase of the cociant-gas Inlet
temperature from 400 to 4500C would produce a relative Improvenent cf the thermal
efficieney of about T.5%. In case of an Increase of this temperiLture to ;BMOC,
Mio thormal officlermy would Increaga by ab,3ut 14%. It will also bsj noted'that a
speolfic Inarl~ane Ur th" Maximum ruol-oloinont tiurfitoo t1ompernturo ((Pon not result
in ths same increase of the gas-coolant tempevature at the rl&.~tav uuLlvt, If the
coolant inlet temperature remains the same. For the design parameters of the
Czechoslovak nuclear power plant (maximum fuel-element surfa3e temperature = 5000V;
gas-coolant inlet temperature - 95OC;. gas-coolant outlet temperature - 4250C) an
increase of the fuel-element surface temperature by 500C would result in an in-
crease of the coolant outlet temperature by 40.70C and a relative :Increase of the
.hermal efficiency by about 6%, thus increcsing the original-desiga thermal effi-
cl,2ncy from 25% to 26.5%. There is, however, a number of othcr taotors which may
contribute towards increasing the thermal officiency of a nuclear power plant, such
,as: kdghr-r coolant temperature at the reactor inlet; transition from a single-
pressure steam cycle to a two- or tiLree-pressure cycle, higher steam pressure; in-
troduction of steam reheating; regenerative heating of feed water by steam ex-
Card 2/3

22362
Z/038/61/OOC/001/003/005
The influence of the surface temperature ... A201/A126
tracted from the turbine; intensification of the heat transfer from the fuel ele-
ments to the coolant in the reactor, and from the coolant to the steam In the heat
exchanger; output flattening throughout the active region of the reactor. riot,
the design parameters of the Czechonlovak nualear power plant (29 a-.mospheres,
4oo0c), the transition to the two-pressure steam cycle (70 and 12 atmospheres)
with steam reheat to 4050C, feed-water heating to 1050C, and increase,of the cool-
ant inlet temperature from 95 to 1750C with the outlet temperdture unchanged
(4250C), would raise the thermal-cycle efficiency from 25 to 33%, which is a
relative efficiency increase of 31.5%. In conclusion it can be stated that al-
though a raised fuel-element surface temperature undoubtedly exerts a significant
and favorable influence on the efficiency of a nuclear power plant, especially
since it leads to the improvement of the themal-cycle efficiency independently of
all other factors; there are also other, more effective and still uniised ways and
means of obtaining the same results. There are 2 figures, I table anti 6 referenc-
es: 5 Soviet-bloc and I non-Soviet-bloc. The reference to the E-ngli,3h-language
publication reads as follows: S.McLain: Reactor engineering lectures_._Chi_cago;____----
ANL - 5424, 1955.
-------ASSOC1-ATION.-_O6tiv a ern6ho v~zkuiyu nAV (Institute of Nuclear Research, ~BAV),
Prague
Card 3/3

2AJICI V.s, inz, (Czechoslovak. Socialist Republic)
SwitchIng off of small lagging currento by the high-volt4qe current
braker. Przegl elaktrotechn 38 no.3:8"1 Wr 162*

iZAtTICP V., prof. ins.
Three now pubUcations of the International Electrotechnie,sl
Commission from the field of high-voltage circuit breakers.
El tech obaor 53 no. 6049-351 Je 164.

Ell
lurir.i
_n Lhe region of cn5et si.~rface bo~ ~rg
flow of water in &-tube
T, 5- -F
SOURCE: J"aderna. energie, no. 4, 1965, 144
TOPIC TAGS: heat transfer, boiling,, water, ~Iooling
ABSTRACT: !N~ Report Nc. 5-n-1 In .7;%derna Fnergis only as Czech mid
mulTsl
I. &r. (wdlfiedl; The article aescribus the methods and
glyzg 1,hia rogilts of minaurerionts o~ hijac rronorer on the innar oturb,ce
of a at Mah heat fluxe3 (up to i,3W,000 6Lcal,1(m2)~hr) before %a
OnscL boilin& 0.' Lae ~QolliiZ 'Ind r'. tlho --f t t on
cooled wall of the tube. The paraneters of the head transfer agen: j
te-j-~,era-jre of 10 to BCTOC, a pressure of a,),)rox1r,-ztely I atm, and a 'fe-
Pe -~u- -a ngi~
Zj mt~~ r of 5,0,a)
n 2.1 0
2 t o 10. WM)
SUB GOM~t 200, 13 SLIDIM DA!r9t nonq
UDC; 621.039.5~6.4:
536.2

-------------
wrtar
A.Cc Nk. r11-11R!
r 174,:(- "'V!, Rr-z ~-kdprn---hc v7rzinunni
IL
MAU.: Date~.-.tion of urani= ftiel elemen-A-allurress during inactIve tests in CO sub
2 streams
3-7
SOURCE: Jaderna energ~Le, no. 1, 196
TOPIC TAGS., uranium, reactor ftel element, aerosol, radiomtry
ABS"FEA(ri : A radi tric method of the detection of uranium releasu-xd in an inactive
test loop ~y rod-type fuel element is d,,!,~-ribed. rn comWison irth same chemical
f
~r le'Lectimi of ur LT-L 's-, aerosc Is ~r, t,~e
test IY,-p is simple azid iensit-i-rc.. pa[Acr was presezited r~y .-T
has; 6 figures and 16 formulas. LHA)
SUB CODE: IS / MEM DATE: none M I REF.: '003 / SOV W: 004
C"r'd

ACC M AJ?fOO153M- BM= C=t-- CZ/003ul 510/aNUMfor
AUTECORt Ve
ORG-. Instituta of Rualoar aesearchz CSAV. A" (ustav j4dwmtho vynkm CSkIj
r
TI-LU: ContritntIma to coolIng izt~onslncation at high heat f1=13 USiTtE a r&gg8d
beat excwuva awraw
SM=s Warta energU, v* U, no* 10.' 1965. 369-37Z
TOM TAAS: nuclear reactow, imclesx- ro=tor technology, reactor f"1 eilement
kRSDUC-P : Fuel olownt- ooolimf~ pmbU= wA tha analysis of pwz!~bilities of powr
increases in the an axperiumtAl iMV;4Ation of Leat trans
for intonsificAtIon at a high hoat fime uAng a roughenod cooled tmrface. 111p.vork
rwasented t7 Js Stursao Orige art* has. 6 figares, 4 formUs, I table. LW
SUB Comt .20 SM DM: nom ORIG Wt 006 1 OM RUt OM I S07 PZFt
6 v ~,Z,

f
ZAJIO, Vladimir,'d-. im
Heat transfer in the region of surface boiling of floving water
in a tube. Stroj cae 16 no.3t285-301 165.
1. Institute of Nuclear Research of the Czechoslavak Academy of
Soiencefit Res, Submitted July 16, 1964,

~ ZAJIC, V-, P~Of* I ill low
urrent a."- ~-[; tc"'.r.-
conclition:3 in aItPrrating--- 568 0 164.
j (&vor 51 110-102567-
V01111go. I.,,. t

ZAJICP V.
1-1.11- 1-;.---l.-- -
Conference on the heat and substance transfer In Minsi.
Jaderna energie 10 no.10:389,390 0 164.

ZAJIG, U.J. inz.
j
Jear, Trilwt Lasplare; obituary. El tech obzor 53 no. 2-118
F 164, .

Y."ITIC, Vladimir
Conaeatienceo of the as:rr-triatry In cooling, the far.-I el,pmurts of'
tho 'Weilf-.3 mactor. orftrgie 10 no. 3.71-70 Mr I ti, .
1. f-lujiwir Restlarch lnuLltmtti~ Cz-ochoalovak Acadutay oll' "la-lenoes,

lf*p PPf)f. dr. iliz. (j)rjjdLn); ZAJC, V., ArIz.
R'-"'ark;3 On the revie-w
the b,-,c,k "Technalpy
nating current high-vDitrig. ,yclit
Zi
Obzor 53 n0-4:224-226 Ap -- break
. I'64.

ZAJIGI VI, inz.
International conference on synthetic testing methods of
extra high-voltage circuit breakers. El tech ob2or 52
no.10:565 0 163.
1. Statni vyzYi=y ustav silnoproude elektrotechniky.

_ ---------
ACCESSION Mt. Ap4olgogi
AUTHOR:
TITLE:
Z/0038/64/000/003/0071/00T6
",ajia# Vladimir (Zayits, V.)
Effects of cooling aasymetry of VVR-S reactor fuel elements
SOURCE: Jadema energie, no. 31 1964, 71-76-
TO?IC TAGS: reactor, reactor fuel element, VVR-S reactor, VVH-S reacttw fuel
element) water-modulated water-coolcd rlaactor; reactor fuel element cooling,
assymetry
ABSTRACT: The Institute of Nuclear Rase3rch at Rez carried out a-detailed exami-
nation of the effect ofthe geometric arrangement of the fuel elements In the
VVR-S reactor's fuel core upon its cooling regime. Purpose of study wan an at-
tempt to increase reactor's output. The fuel core In this reactor can contain
52 working sections of 16 fuel elements each. Cooling of these fuel elements is
not symmetrical. Analysis of the fuel elements showed that their spacing in
the working sections has a very decided effect upon the progress of cooling and
shape of,the Puel core during the reactorlu operation. Authors also fou;ad that
nonuniform cooling will also cause a deformation in the fuel element. -- Surface
Card -,-1/2

ACCESSION NR; AP4olgogi
boiling of the cooling water will stabilize the progress of deformation, for the
surface boiling effect greatlyimp.rovea the-cooling-proce4a and reducco the
originating temperature-differences. The fact that Boma of the alumintia-coated
fuel elements which 'were used in the tests were probably cooled for a long tize
by aurface boiling without being damaged by the frequently repeated distortions
in the reactor power level attests to their excellent resistive capabilities
leads to the conclusion that a fuel element of tbia-type-la-much-wrii--ii,,Ot-i~iont
than has been heretofore- dete-&m'Lned.-141~o-iir-c~ou-med safety of cooling tho fuel
corc--by-gub~ra-cew "-tr boiling calls attention to the possibility or its being
applied for a predesigned, intensification of reactor cooling while raising its
power level at the same time. Orig. art. has: 10 figures and 32 equations.
ASSOCIATION: Ustav,jaderacho vyskumu CSAV, Rez (Institute of nuclear re.3earch)
SUBMITMED: 00 DATE ACQ~- 23mar64 -7-F-Kc
-----------
~ Ns-
qo REF Sovi 006 02M 014
Ccrd 2/2

uI ZAJIC., Vladimir
i
Some problems in increasir7 the output of the VVR-S reactor.
a
Jaderna energie 9 no.6:200 Je 163.
1. Ustav jaderneho vyzkwmu, Ceskoolovenska akadertie ved,, Rez
u Prahy.

ZAJIC, Vladimir
~- . ~ , , , ~- ~. , - 7 JP " *~ :' --~' -
ftamination of the hydrodynarnit~ and thermal character-ititic-3
of the UR-3-nuclear reactor. Jaderna "nergia 9 no.U &
1347-352 163.
1*'Istav jade=eho v7skL=g CbskosI07enska akademia ved,
Rez.

q
ZAJIC inzh,j FANUp J,p In$.; C.Sc.; GERTp R., Inzet Mcall
JMV, J.,, ins., C.Sc.
Svitching of large shunt capacitor banks for reactive pcmer
compernsation. Bul EOU no.576sl-10 162.
1. Statni vyzkumy ustay silnoproude alaktrotechniky, Buchovice
(for Zajio and Panek) 2.Vy*Umnyustav energetickyo Brno (for
Gert and Jirku).

BERVAR, Marjan, sanitetski pukovnik, dr.; SUDA-RIOV, Zi-vcjln, HanAtet-ski
pukov-nik, docent, dr.1'. WIG, Zivorad., saniteiski po".7.1krjVnik~
. dr. --.- - - -I, !.,.---,-,- - ~t
Organization of the collection of mass casualties during first
critical hours after a disaster. Vojnooanito pregl. 21 no.lla
695-702 17 164

7-kjlc, Ziiorad, sanitetaki potpukovnik dr.; DUNJIC, Slobodan, sunitetski
dr.
Fractures of the patella. Vojnosanit. pregl. 22 no.12:766-774
D 165.
1. Vo.-Jinomedicinska akademija u Beogradu, Klinika za himroke
bolesti.

(;URGlr-v'Ktlm4, sanit0taki pukovnik prof. dr ~ UJjQjivoradZ sanitetski
potpukormik dr
Biliw7jleus. (Case report). Vojnosanit. pregl. 19 no.9:6)"38
S 162.
1. Vojnomedicinaks Akademija u Beograd*, RadioloaXi inatitut,,Klinika
sa hirurske bolesti.
(INTESTINAL OBSTRUCTION) (CHOLELITHIASIS)

UJIG) V., inz,
Experimental laboratory.fw high-tension currents, the
department for short circuits in Bechovice. flova
technika 2 no./+:108-109 Ap 157.

ZAJIC, V., dr.
Electric liqAd level indicator. Jemna mech opt 6 no.2.-45
F 161.

- ZAJICJS V.
Drivirg of turbines of nuclear plants with boiIipg-cojjxnn
reactors. Iaderna energie 6 no.6.-209 Je 160.

A now control device for nuclear reactoro. Jaderna energie 6
np.6:215 A 160-

3124621OW1019/0CV006
IW7/1207
Z,ajic Vladimir
TITLE;% Kethod of tianuforL&iiq; circular into rectilinear LAotiom
PZLaODICAL: Ruferativny vhurialt otdellxqy vypusk. 4~* Silovyye uatimoviski,no.1%.
1962, Wt abstract 4219203 kCzech patent, -class 47 h, I., nq. )-7833,
Deceiaber 15, 1~60
T"T t A. Laehm4am ia pr9posca to ve used, in re6Aaatora, automatic devices,
etc. JA the raechmisla, the Iinmx diaplacuwaut of a rod between its guides iu
proportional (with an accuracy of about 044) to the kotation angle of another rod
withiu the iii4its of + -300- Tht: r4conauism is reversible. There is 1 figure.
Abstractor' a Aote; Complete Muialation. j
urd 1/1

IMO.a 7l..p dro, In7l, , ,
BUctrlo lov6l fo*Ur. &r=-.mqch opt, 5.no.12:383"385 ~D 160.
L C'eakoolovenska akadoLde ved,, Prz~,

1413189
Z/032/62/012/010/002/002
n6o/M35
AUTHORS: Peprny', J., Engineer, ZaJfc, V,, Engineer 'Doctor
TITLE: Mechanized wind tunnel for testing blade cascades
,PERIODICAL: Strojfronstv:(, v.12, no.10, 1962, 774-780
TEXT: The authors describe an experimontAl wind tunnol where the
...running parameters, such as air temperature, velocity of air flow*
velocity and static heads befori the cascade, velocity and static
heads as well as direction of air flow-after the cascade, are
automatically controlled. Relevant reading* monitored are
evaluated by special analog computers containing mainly mechanical
elements. For air temperature control the,tunnel is provided with
a heater of 10 kW output 'supplied by a d.c. generator which is
switched on and off through a relay, actuated by a thermostat.
The, temperature is maintained within + O.jLCC. Air' velocity is-
regulated with the help of i Ulo-;-o7f valve operated by a
servomotor, itself actuated through an electronic circuit by a
aticro-manometer in which the regulated pressure is balanced against
the atmosphere. A needle contact with one of the surfaces in the
miceo-manometer brings the servomotor into oper~ation. Velocity
'Gard 1/3

Mechanized wind tunnel
Z/03i/62/012/'010/002/0'02
Fu6o#435
is maintained at a constant value within + 0.250%. Three-hole
probes are used for monitoring velocity aiid static heads before
and after the cascade. ~he upstream probe is fixed, whilst the
downstream one is automatically placed, with the help of a
servomotor and a special micro-manometer equipped with contacts,
so that tile middle hole faces exactly the dirpction of flow.
Readings are fed into three analog computers which give: static
pressure behind the cas"de to enable correct positioning of tile
plane of' traverse to be effected, mean velocity head and outlet
angle as well as recording individual values across.the traverse
and, finally, the aerodynamic force on the blade. Static pressure
behind the cascade can be,continuously checked on a bank of
manometers consisting of.,three U-tubes. Static pressure is
derived front a difference,of total and velocity heads.' The bore
of the two manometer tubes involved and densities of liquids
they contain are arransed.so that direct reading of static head can
be obtained by a simple operation of a cursor.. The third,tube is
used to check that the probe faces the stream. A detailed
description is given of,the computer for integrating velocity head
Card 2/3

2/602--!
Z/032/62/01i/Oi0/00a;
Mechanized wind tunnel ... n6o^435
readings in preparation for the calculation of thq mean value of'
the velocity head, The operation of the computer is each'time
.~,initiated from a control panel by simply pressing a wwttch.
Though certain arithmetic operations still have to be done
:[manually, it in estimated that this repreadnts only 101# of the
"total work. A descript*on is..also given of the computer for the i
1%evaluation of.total aerodynamic'force on the blade which 'baves
laborious manual calculations and'recoiding.. The tunnel
accommodates blades-15.75 inches long with a depth or profile
-2 to 4 inches;, maximum air flo /min at room
w Is 5720 auble feet
temperature and at a maximum air volocitY, OC"183 feet/seq,
There are'12 figures.
t Piz A.0a Pe
ASSOCIATIONSI.LZ, en prny)
CSAV, Prague (VO-Zaj:Cc)
r
Card 3/3

3/!94/62/000/004/001/!05
AUTHOR: il~J19A_yl A i Mi w
TITLE: Analog devioe for modelling aerodynamic forcoo (pa-
tent)
PEI~IODICAL; Referati",yy zhurnal, Avtomatika i radioelektronika,
no# 4, 1962, abstract 4-1-33a (Chekhosl. pat., kl.
42k, 4, no. 97419, 15-11-60)
TEXT:' An analog device is patented for the modelling of the aero-',~-~
dynamic forces arising due to the air flow around an investigated
object, which is characterized by simplicity, sa7tisfactory accuracy
and by the fact that there is no need for graphical or grapho-ana-
lytical"processing of the.results. The essence of the device is in-
the use of a liquid pressure gauge (see Fig. 1, 2), containing two
groups of tubes which can rotate to any angle around t;ie axis 7.
The number of tubes in each group can reach 15-- The internal dia-
meter of the tubes is 6 mm, (some-of the 'tubes have a diameter,of
-3t 4 and 5 mm). The tubes marked 1 are filled by some liquid 6
Card

6/194/62/000/004/001/105
Analog device for ... 'D222/D309
(H 0, C H OHI Hg, etc.), whose parameters determine the limits of
2 2 5
measurements. The positions of the tubes are fixed by *the supports
4 which rotate around the axis 8. The lower ends of the tubes are
connected via the rubber tubes 2 to the container 3 and to the
measuring tube 5. The upper ends of the tubes 1 are joined to the
probes a9 b, c, d and e, which are attached to the investigated
profile 10. The pressure P. arising in the probes is transmitted
to the liquid in tubes 1 rotated with respect to the vertical
u
through an angle corresponding to the angle between ihe normal
to the profile and the axis z. The resulting value of the measured
aerodynamic,forces can be obtained by reading the head 9 of liquid
in the meaat'xring tube 6. Formulas are given for the calculation of
the aerodynamic forces,"A second group of tubes, Joined to probes
go h, ij j and k, is oonndoted to a second measuring -tube in the
same way. The total value of the.measured aerodynamio forcoo oan be
obtained as the difference of the readings from the Vao measuring
tubes. Measurements can be carried out by the compen3EI,tiOn method
by applying a pressure Ps at the upper end of'the measuring tubes.
Card 2/3

S/194/62/000/004/001/105
Analog device for D222/D309
3 fi'ures. /-Abstracter's notoe Complete tTanslation.-7
Fig. 1
Fig. 2:
Card 3/3

ZAJIC; Vladimir
Development of homogeneous reactors and the experiewAt lwl,fh
the Czechoslovak Project. Jaderna energie 7 no.9:296-~M-
3 161,
1. Ustav Jaderneho vy2kamu, Caskoslovenaka akademie ved,

"Iftva
S/261/62/000/01 0/001 / 001
100711207
Authors: Zajic. Vladimlr
Title AuToMATIC SIMULATING (MODELLING) DFVICF FOR IMPELLER-TYPE (VANE)
PUMPS [Abstractor's note- incomplete translation of the original Czech title]
Periodical Reforainn)y zhurnal, 10, 1962. 17, abstract 34.10.13211 (Cmch. pMcm,
class 42 m. 14, no. 91679. 15,09,59)
Text. No abstract
Card 1.11

27397
Z10381611000100910021003,
D257/D305
AUTHORs Zajic, Vladimir
TITLEs The state development of homogenous reactors and experience
with a Czechoslovak project
PERIODICALt Jader-A energie, no. 9, 1961, 296 - 300
TEXTs In 1956-1959 the fistav jadern6bo vyzkumu 'CSAV (Ir-stitvte cl' 'N1u.-:7?ar
Resea-rch. CzAahnslovak AS) studied the problem of homogenouF rt:a.(,Toiu ior
power productim When it was found that technical difficulties connected
with the development of a safe h,Dmogenous power reactor would require many
more years of research and development, the project was abandon~-d. Thit p&-
per presents a brief review of the results obtained from the st-,~Ay and liits
the bibliographic references in which these results have be~-n deet.'~ -.,itlh in
detail. The research project considered two types of homogenous
(1) A small (active zone about 500 liters, output 10 - 20000 kw(-h) )' OyE3-
tem using medium-enriched (uo to 20% U-235) fixel without reflector and
light water as moderator, to be used in portable packaged power iitations;
Card 1/5

27397
Z/038/61/000/009/0u/~DO3
The state of development ... D257/.D305
(2) A larger system using slightly enriched (about 1% U-235 or Pu-2391'
fuel and heavy water as moderator which would be capable of sever%l y'E'.r3l
operation when refueled with natural uranium (in the form of oxiie.) 0n-4.7.
The study produced the following results: (1) It was determined 1hat a
hea water moderated power reactor of a sufficient large size ( about 20
cm37-with slightly enriched (1% U-235) natural uranium as initial fuel
could be operaAed continuously as satisfactory parameters ( 2500 C ), U~Ilng A"
recycled plutomium and natural uranium for refueling, and thus at,~Pirirc, a
fuel burnup(of 3000 - 10000 mwd / ton. (2) The cylindrical react:)r preas-
ure vessel 120 atm ) for the smaller hype ( diameter 750 mm, height 1800
mm, weight 2,500kg ) could be produced from 13123,1 high - strength carbon
steel plate ( 60 mm, thick ')-with a continuously welded-on sta'Anlf_,:3s-,sts~!
lining 8 mm thick ). The piping could je produced of AVVexS sta:~nlesp_
steel 0.1% C, 18% Cr, 10% Ni, 2% Mo, 0.5% Ti, 69.4% Fe ). (.3) Sieveral.
original concepts of the active zon*~.and other partn of the prima~,y cir-
cuit were suggested. Also, original "thodoof fu6l, recycling, doeting and
storing, as well as a system of recombination of radiolytical per~-
mitting utilization of the released h'nat for power production, vere
Card 2/5

27397
Z/038/61/OO0/CO9/C02/C,03
The state of development D257/D305
worked out (4) It was found that a reliable pump with high operat-Ing para-
meters (30;0 C, 120 atm) could not be produced in the hR due to the 14ck
of adequate insulation material for the driving electromotor, 0..-1 the Other
hand, if natural circulation were used the reaction would yield only 20 --
30% of the speciiic output and, in addition, the hazard of sedijaantaticn of
the solid phai3e of the suspension would increase, Forced circularion D-.~
meansof pressurized gas was found impractical for this reactor type. (5)
Granulometric studies of the fuel (U 0 ) particles reyealal thai~ a 3izv- spe-
ctrum of about 8 microns would have ~o8be mati'ita'ined durin'E' b4tirtl oper-
ating time. The pro4uction process of such fine particles i~s ccra-,ezTedl with
great technical.difficulties and has to be performed at tempera"urei ,cnel-
derably exceeding 10000 C. Also, the separation of fission produrts from '.-he
fuel suspension was found difficult and expensive so that it was cono - ded
that the development of adequate and oconor.!_,,a1, fuel processiric wcuad rtiqui-
re several years of work. (6) Safety studien r)venled *IhaA; it fo~' rapoc, ~,y
IL 10 Mw(th) roactor under concideration would produce -Piaoicn -,rt-h
a total activity of 1 million clarie daily. Since maintenance and repair by
I A-k
current technical means would be impossible, it would b9 mandatory that 'he
reactor operate trouble-free for a number of years, This, hvjs~,ai~, is a.-. 'rc-
Card 3/5

27397
z/03Y6 1/00O/o0Vr'02./-')'3 7
D2", 30~:~
The state of development J, II I
tremly severe requirement which is utterly new in the field of Power pr')du-,-
tion. The above results have led to the fOllowing conclusio"ric, h,-j-
mogenous reactors with their easy fuel repar-ition, simple a~rran~,pme- of
the active zone, fuel breeding, and rer~y,:Iing 01'.fer rreat
advantages, these cannot be utilized until a reliable, trouIbI'e-J'::-r-ej iong-
term operation of these reactions is secured, At zhe present tizu', cnly
low-power homogenous reactDrs for experimeara. work, optirating ti.i. Io T,
rameters (preasure, temperature, flo~w rate oil Nel. cvxapenaion~. cj' til.? pr.1-
mary circuit oan be considered reliable. T))e,'r uae for power
would involve a great q7.xantitative laap whi,:,.a would require grent -A'forl-~
and large fineno-Jal means to ac,7omplish. Appre_-.Iation is e.Y_t'LrIJad t- Engi-
neers. V. Stach and P. Kovotn.~. There are 61 references, j and A-
9 non-Soviet-bloo. The four most recent referenrFIfi 4.,,) F.11? I'llb
lications read as followss Lfino, 11,.C. M~zYnar.;~on, F. Maslla.nj PI"I'll "Oue!
Reactors, Addison-Wesley Cog Reading, Mai:s., USA, 19581 K.Cohen, 1. Zebros-
ki, Operation Sunrise, Nucleonics 17, 1959, 3~ 63; S.E. Beal e,, a!.., Th-a
Homogenous Reactor Experiment No 2, Ref. P/449s Geneva 1958, Alloiai-- R,~-rj.ew,
Engineering, 1959, no, 4a86, 606, Jadern~ energie 6, 1960, 5, -6,),, (Te2h-
Card 4/5

fin]
27397
Z/038 16!10001009~'00-2.10~~',
The state of development D2577D305
nical Edit ori J. Berhnek
ASSOCIATIONs Uetav jadernfiho vkzkumu CSAV (Institute of Nuclear Re2earch,
Czechoslovak AS)
PV--
Card 5/5

84748
Z/038/6C,/000/006/003/004
u3o R(ad&O A20I./Ao26
AUTHORt Zajfc, Vladlm~_,,
TITLE: ~Qpecifio Heat and Thermal Conduotivitylo"' Powderized Jranium Oxidel-I
U308
PERIODICAL- Jaderna energie, 1960, No. 6~; pp. 200 - 201
TEXT: In conjunction with a project of a homeneous circulation reactor
with U3% suspension in light water (Ref. 1), the specific heat and I al conduc!
tivity of powderized, U30 were exp- eri mental ly Investigated. A rrocLified calorime-
tric method (Ref 3) was Reveloped for this purpose,,which yields more reliable re-
sults than the Woestyn method (Ref. 2). A specimen of powderized IJ309 of grain
sizes ranging from 3 to 8 microns, a dry-tralk density of 2,3 &/cn*r3, a bulk density
in water of 3,2 g/cO, and a crystalline density of 8.3 9/0m! wa~~ u8ed. Thin ape-
cimen was dried for 48 hours at a temperature of J400C,, Then thf,! sperimen was pla:~-
ed into a cylindrical vessel 50 mm high and 30 mm In diameter, made of brass sheet
0.13 mm thick. A schematic diagram of the vessel is shown in Figlire i where 1.
Is the cylinder wall; 2. the upper lid; 3, the lower lid; 4. the eyellmt for
suspension; 5. the cover of the filling opening; 6, 7,.-, 8, 9,, 10-Ints nolder-qd
with tin: 10. the suspension wire; mid 11. the powderJzed spevtmeri, lbe. density
Card 1/3

614746
Z/()38/60/000/)06/003/oO4
A2011A026
Specifio Heat and Thermal Conductivity of" Powderized Uranium O.xlde U31)8
of the powdertzed specimen, as packed Into the vessel, was sup8-3,78 g/cM For
a temperature range of 211 - 980C. an average specifio beat value "UV8_0 6'193~
+ 0.00024 kcal/kgOC was obtalned, 7nis value differs from that. obt.0ted by the
Woestyn method by 13.85%. but. 1z in good agreement with the specific heat values
of U02 and U03. The U308 thermal conduct!-vtty was derived from the ~Jtanges of the
temperature T with time -C, as plo'~ted during the heating of the stirr4id calorimeter
water after the immersion of the !~peclrrer_ (Figure 2), The valve. was calc,,J-
lated from the equation for non-stationarl heat tranifer by condunticn, assumIng V~
a constant Incipient temperature Tp through the entlr~,~ YnIume of -thv teated spednEr,
(before its imm,3rsion) and a constant surface temperature TC' of thr! s~eclm-n during
its 'cooling in 'che calorimeter, The sol'ition y"elds ar. average thermal conductiv!-
ty value AU308 - 0.1193 + 0.0017 kcal/rrh'C for an ac-tual spec.MC-n den Ity s-3~78'
_q
9/00 and a porozity of ~4,5%. This'-aiue :is In good agroement wi.th re'eults ob-
tained by V.S. Chirkin (Ref - 8) f or the thermal -conductivity of powderized 1300.
This simple method can especially bp osed where the contanitoation of 4,ie calori -
meter medium ha~- to be avoided and whern T-he s~.ibstances rrea~ured iv~t aot be dl---
fused durIng the- measuring operation. There are 2 figures and 1-I referencez~ 5
Card 2/3

847h8
Z/038/6)/OOC/'006/003/004
A201/AOM -
Speoific Heat and Thermal ConductlVj4y of Powderized Uranj.um 11 ~de U 0
1 Ixj 3
Czech, 3 Soviet, I East-German and 4 English,
r
ASSOCIATION: Lrstav jademeho vyzkwu C-SAV of Nunlear Research), Prague
Card 3/3

~ Z-Ajic-t V.
IXM3~c -

C72CUMLOMM/Nuelear Mysics - Nuclear Techail-ILV 611d Piwer. C
Abs jjiAr : rv~4' Shu': ND 12, 1959, P-69go
Auth)r i Zajic, Vladirdr; Kam-, Jarislav; GrcC;)r, jan
Inst : Institute Df Nuclear Pl,ysics, CzLc'A,,L)sljvak Academy
~)f Scicaces
Title ; Praject -)f Experimental 11on-)L;f-,m)us Ten MeLp-watt
Reactir with Circulatilir* Fupj. suspensi~)II of Uraniun
Oxide in Lidit Water
Ori[: Pub : Jaderna 1958, 4, 11) 12, 361-365
Abstract rk-- s c r 1.
ption af a prDject of n hjmjGene-.)vs tci,, m,~pwatt
react.,)r with c-'rculation of tLe fuel suspension Df
urnniun ..)xi(le iii 1jeavy water. Results are C~vcn ~)f
the calcl-dabi,)n ii! the critical pararmtera :11' the
reactDr and the principal scheme )f the pr.','1'3,,"iry
cj-)lant 1:~.)p ia described. - P.P. S-)senk--)
Card 1/1

vial
AA
AA.
Ilia
Ini
11 A!
'94."o

Elektrotechniciq Obzor. Praha# Cze4hoslavakla. Vol. 47v no. 10t Oct. 1958.
Monthly list of last European Accessions (EFAT), W, Vol. 8, No. 6, Jun 59, Uncles

CzEcHOsLC,VAKjA/Nuclear Phyeicd .. Nuclear Technology and Power.
Abe Jour : Ref Zhur - FiziY4, No 6, 1959, 12637
Author : Pfann, Jaroslav; Zajic, Vladimir
Inst : Institute of Nuclear Physics, Prague, Czechoslovn:!Lia
Title : Nomographic Solution of Critical Equation for a 1.iclear
Reactor, and Its Application.
Grig !?ub : Jaderna Energie, 1958, 4, No 5, 114-122
Abstract : An analysis is made of the mathematical formulatien of
the critical equation for a nuclear reactor, and a nomo-
&-am is plotted for the calculation of the critical ra-
dius of a spherical reactor, alont,, with a plot fcz- recal-
culating the results for reactors of other 3hapes.
Card 1111

f9
Latr: 49P30 IOSY
lam
J;ILS w 0 iThere
the rmw izA,Ltkkug
the'ao'nompix tk crit.
gme, wAgghs Ityz tM
o1
I ddcja an Pflg-t"" r"'
Y, Th, influcace of a rcitecu
From
naL. bt

ZAJIC V.
TECHNOLOGY
PMCDIC9~'St JADERNA ENERGIE Vol. 4, no. 12, Dec. 1956
ZAJICP V.t PFANNI J.s GRMCR9 J. DesIgn of an experiKental 10 nw. homo-
gencus reactor fubled with circulating uranium oxide suspension in light
water. p. 361
Monthly List of East European Accessions (EEAI) LC Vol. 89 no.
May 1959, Unclass.

Technical standard and further development of short-circuit testing station* P. 30.
(Czechoslovak Heavy Indatrys No. 5,, 1957. Prague, Czechoslovakia)
SO: Monthly List of East Buropean Accessione (EEAL) LC, voi. 6, no. 10, October 1957. Uncl.

ZAJIC$ V.
14ission and facilites of the short-circuit test establishment In Czechoslovakia.
Pa. 3.
(Czechoslovak Heavy Industry. 1o. 5, 1957. Prague, Czechoslovakia)
30s flonthly Liet of E_jot &iropean Accessions (E AL) LC,, vol. 6j no. 10# Outobeir M7, Uncl.

Zhilet V.
A review of !x-direct methods. P* 3790
(glaktrotafticky Obzoro Vole 46,0 no. 7# July 1957. Prahaj. Czechoolovakia)
80t Monthly List of Eas,%'# European Accesaions (EDI) LC,$ Vol* 6., no., 10, October 1957. Uncle