SCIENTIFIC ABSTRACT YEGOROV, Y. A. - YEGOROV, Y. M.

• Document Type: CREST
• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R001962510010-6
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 100
• Document Creation Date: November 2, 2016
• Document Release Date: September 1, 2001
• Sequence Number: 10
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

ACCESSION XR: AP3004886
t
olution, etc. Anal g the optimum delay time!
ee yals of the results permits selectin
In the control channel, resolution time of the coincidence circuit, permissible
loading of the t4pectrz)rneter, and its block'schema. A comp~rlsoyl of several ver-t:
siona of the spectrometer showed that the beat composition is a mixture of equal
amounts of vllol (or phenyleyclohexane) and trimethylborat6 with B10 enriched to
80%. The resolution time of, the coincidence circuit must bd 1. 5 microsec.
Orig. art. has. 7 figures, 6 formulas, and 2 tables.
ASSOCIATION: none
SUBMITTED: 3lAug6Z DATE A CQ: 2BAug63 ANCL: 00
iSUB CODE: NS NO REP SOV: 005 0-kHER.- 00 1
Card-
MINT
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,-,"YEGOROV, Yu*Aa
Simple circuit for a device for tooting electromagnetic relays.
Priborostroanis no.10:27 0 163. (MIRA 16.-11)
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Pc -4/
EWP(J)/EPF(C)/SPF(n)-2/EWT(m)/BDS AFFTC/ASD/SSD
1,,,1286o-6A Pr.-4/PU-4 RM/W4/DM
S/0089/63/015/001/0017/0020 7Y
CESSICU IM' AP3003970
AUMOH: Aywycv.l V. 1,10,; vAsIllyev, G. A.; Vezel-kin. A. Yegorov, Yu._A*; VAN
Orloy, Yu. V;,Fankratlyev, Yu. V.
No
EM
no
TITLE: Feactor neutron fluj attenuation in polyethylene
t-----,--SOMCE:-Atcmnaya7energiy-m,---yi--15---nii.--l-,-1963i-17-20-------
-enuation, polyethylene,,polyethylene neutron attenua-
TO-DIC-TAGS:, neutron att
tion, slaw neutronY fast neutron, neutron relwmtion lengthY biological
shielding, water-,rater reactor
ABSTRACT: The attenuation of fast and slav neutron fl=ea by polyethylene
has been investigated experimentally in a water-!vater rescgxch_reactp~~?
A polyethylene 680 x 680 x 1000-MM prism consisting of square plates 10 ank
20 mm thick was irradiatedIC placemeet in a recess in the heavy concrete
shielding of the reactor. The slov neutron fluxes von me-suied by the use of
resonant indicators (indim, iodino) and a BF, counter. The fast neutron
distribution was m=-urcd by mean3 of threshold indicatoes P(n,p), Al(n,v),
end Al(n,a" and a scintillation counter with ZnS(Ag). During meazurc=cnts the
plane indicators were inserted into Gay5 betveen the polyethylene plates, and
Cor4 Vkl-

L 1286o-63
ACCESSICH IM: AP300,3970
the cylindrical indicators were placed into 20 x 20 x 100-m holes cut in the
plates. The results obtained are shain in'rigs. I and 2 of the Eaclosure
along vith theoretical data obtained by the met-hod of mcments for a poiw,,, neu-
troa source. A ccnparlson or neutron relaxation length in polyethylene (den-
sity.. 0.92 gfemn) an& in water =der Identical conditions showed that thvi rc-*,
laxaticn length in po3.yethylene Is 12-1rp shorter than that in water. "The
authors thank the reactor operating personnel and laboratory technicians who
took part In the exT.,eriment." Orig. art. has-, 2 figures and 4 tablead
ASSOCIATIMT: none
S
MITTED:
M 25Avg63 DAT?, AcQ: oMugO ElIft: 01
SUB CCDE: ITS rio mr, sov: oo4 mm o04
Card 2/1;~

~-6 FWP(j)/EPF(n)-2/ZWT(m)/BV8. AFFTC/ASD/AFWL/SSD.
Pc-4/Pu-4 -
ACCESSION NH: "3003971 q/008q/63/ol5/001/0o2q/oo22
A=0R: ~Vmyev, V. N.1 Vasillyev, G. A. Veselkin, A. P.;
Orlov, Yu. V. t . Pankratlyev. YtA. V.
TITLE: Qpg_c_tm_ of reMtor fast neutrons saed through p2jySthyjaqe~
SOURCE% Atomns-ya energiym., v.,15., no..I., 1963j, 20-22
-70PICTAGS: fut neutron ispeatm, polyethylene, reactor'shielding
AB3TRACT: , 1,Sasurewnts were made of the opectm of fast neutrons after Tass&LYA
through a. layer o46' polyethylene plates Wo x 68o x lo mm) installed in a recess
of the shielding of a vfttar-wata~r reactor. The thickness of the polyethylem
layer was increased on the side facing of the spectrometer detectors. The
p measurements were We by mans of a fast-neutron spectrometer with a single
detector in which y-background discrimination vas achieved by mans of a space
charge between the last dynode and anode of the photomultiplier. The fast-
neutron spectre, were determined.from the amplitude distribution of pulses pro-
duced by recoil protons in the stilbene crystal cif the detector. The spectra
were corrected for the effect of secondary neutron scattering in the crystal
end for partial leelmge of.recoil protons fr= the crystal.. The results obtAined
:Card V3
Ri

A=MZO',( NRt AP3003WI
are ahm in Pig. 1 of the Enaloaure along with th3 results calculated by the
method of moments (shown by th~ solid line). The masured spectra were found
to be in Sood agreement with U!eoretical result"a for all thickneases or
po%yethyicne Wer at % > 3143v,. At E a < IVO
v & divergence betveen the ex-
rimental and calculated results was noted. Hotever
0 the tendency for & chs n ge
P
in spectm with an increase in layer thickness in this energy range was the
i some for both calculated and experimental spectra. At neutron energies from 3
-,..-to 4 ~bv and polyethylene thielmesses greater than 20 9/cm a , the curve of the
measured spectra shoved s. sharper dip than tl*At of the-qalcuI&te(~.spcttr%. This
is probably duz to some inaccuracy in selecting or avere-gin 1~-thevcro3s sections
during calculation. The "rper dip in the curve waa also noted in neutron
spectra measured in-vater. 117he atxthors thank their coworkers w1io serviecd the
reactor and laboratory assistwits who assisted in the carrying out of experi-
ments." Oris., art. h"i -1 figtwe--
ASWCIAMON.- nom
SMIMM. 2paxz62 DATE: P=1 OSM963 ENMI - 03.
EM COM: NS NO ESP sOvt 003 qTWR:' W2,
Card 2/3
M-17

S/0000/63/000/000/0190/0192
ACCESSION NR: AT4019047
AUTHOR: Yegorov, Yu. A.
TITLE- Deformation of the spectrum of fast neutrons in concrete and water
SOURCE: Voprosy* fizild zashchity* rc~ktorov; sbornik statey (Problems In physics of
reactor shielding; collection of articles). Moscow, Gosatomizdatj 1963, 190-192
TOPIC TAGS: nuclear reactor, reactor shielding, concrete shielding, water shielding,
neutron, neutron spectrum, neutron spectrum deformation
ABSTRACT: The author discusses measurements of the spectral deformation of the fast
neutrons of a nuclear reactor as they pass through thin layers of concrete and water,
carried out In 1955 on the nuclear reactor of the AN SM. The spectra were measured by i
means of a fast-neutron scintillation spectrometer with two sensors. The reactor neutrons
were removed through the lateral experimental channel of the reactor and passed through
a 1-meter-thick graphite reflector and'16-millimeter-thick steel plate before reaching the
spectrometer. Spectra were measured in an ener of 2. 1 - 3. 6 Mov. The spectronieto
was calibrated by the measurement of theo(- and;r-s'pec'tra of several radioactive radiation,
a
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ACCESSION NR: AT4019047
sources. The transition from the energy of thect- andQ -particles to the protoq energy
was made on the basis of the information contained in TaylWs paper (Taylor G. et al. Phys'd
Rev., 84, 1034 (1951)). The spectrum of the fast neutrons behind the reflector of the
reactor has a ma)dmttm'at an energy of 2.36 Mov (See Figure 1, curve 1 In the Enclosure);
the number of neutrons at this energy level Is approximately 40 times greater than the
number of neutrons at the maximum energy. 7be fast-neutron spectrum behind the re-
flector Yers in form from the spectrum of the fission neutrons. Ile spectrum behind
t
th
,e ref,:~
c,
tor becomes monochromatic around the 2. 35-Mev energy level. Ile results Of
the measurement of the spectra of neutrons passing through thin layers of concrete are
shown in Figure 1. Curve 2 was plotted for a concrete layer 5 cm thick; all the other
curves were plotted for a 2.5-cm increment in the thickness of the layer. It will be
observed that the appearance of the spectra Is not very different from the spectrum of fast
neutrons behind the reflector.. Approximately the same change In the fast-neutron spectra
is noted as the neutrons pass ihr6ugh water layers of small thickness (See Figure 2. in the X.,
Encloffure~ la this casQ, however, the change in spectral form occurs somewhat more
rapidly than with the neutions passing through concrete. Thus, with the thickness of the.
water layer at 20 cm, the spectral maximum of the'neutrons occurs at an energy level of
'2/6
Ml

ACCESSION NR: AT4019047
2. 15 Mev. As the thickness of the *ater layer is increaaed# the bo~zwary energy of the
neutron spectrum decreases. 0rig. art. h4s: 2 figures..
ASSOCIATION: none
SUBbUTTEDt U Aug63 DATE ACQ: Mob" ENCL: 02
OTHER: 003
SM CODE: NP NO REF SOV's 003
13/5

Spectra of the passage of fast neutrons thicuifi c~niiiWiaj~rs of various
LFiguro 1
knees: 1 -spectrum behind the reactor reflector; 2 - 5 cm; 3- 7.5 am;
N
tb!c1O cm; 5 - 12.5 cm; 6 - 16 cm; 7 - 17. 6 cm and 8 - 20 cm (NOTE: LegendI
4
to left side of figure reads: "number of neutrons, relaitive units"; legend beneaN
.,C r f to
reads: I,neutron.energy in megaelectronvol
YIR11 rl~~2,
1' N. ~R~ "N"',
F:~
'Y 7

ACCFZSION NRI AT4olqo47 EM=(ME: 02,
'0 O-C
Ot
44
41Z
Spectra of the passage of fast neutrons through water layers of various
thickneeal 1 -'spectrum behind the reactor reflector; 2 - 2.5 c9l 3
czal 4 - 10 cmI 5 -.20 cm (NOM Ihgend to left side of figure readei
I.Inumber of TAutrons, relative units"; legend beneith figure reads:
,-J-r 1 5/.5 'Iftutron energyAn segaelectronvoltall)

ACCFMION NR: AT4019056 S/OM/63/000/000/0229/02M
AUTHOR: Veselkin, A. P.; Yegorov,, Yu. A. Panov, Ye. A.
TITLZt 71w passage of Gamma-radiation throuo a flat alit In shielding
BOURCE: Voprosy* fizfld zashchity* reaktorovf abornik gtatey (Problems In physics of.
reactor shiolding; collection of articles). Moscow, Gosatomizdat, 1963,,229-234
TOPIC TAGS: nuclear reactor, reactor shielding, Gamma ray propagation, Gamma ray
attenuation, radiation shielding, shielding structure, lead shielding, steel shielding#
plexiglass shielding
ABSTRACT: The authors studied the weakening effects exerted on' radiation shielding by
slits and discontinuities (heterogeneities), noting that e3dating formulas and techniques for
computing the passage of radiation through slits &W vwwjms an applicable only If certain
accepted limitaVons us fulfilled and in.no, case encompass the entire varitKy of possible
slit and vwwtm forms. As a source at )(-radiation a linear isotropic C*180 source was
employed, which was simulated by the forward movement o( an isotropic point souros (See
Fig. 1. In the Zadosure). The does was measured by a sointillation Y-dosimeter. During
cowd

ACCESSION NR: AT4019066
the experiment, the dose intensity was measured over a length of 160 mm along th6 shielding
in a direction perpendicular to the alit. 7`he authors Investigated the dependence of the dose
intensity behind a slitted shielding on the properties of the material used to fill the slit as
well as on the properties of the materials of the shielding itself. As shielding matdriale,
load and steel were selected, while steel, titanium, aluminum, carbon (graphite with a density
of 1. 65 g/cm3) and organic glass (plex1glass) were used to fill the alit. In all raeasuremients,
the thickness of the shielding was 120 mm and the height of the slit - 20 mm. As expected,
the intensity of the dose behind the shielding rises sharply as the specific gravity of the
material filling the slit decreases. 7bus, for example, when steel Is replaced by aluminum,
the dosage.intensity opposite the'center -of the alit increases by a factor of 6. 5. Explanations
for this fact are advanced, and the concept of the specific dose (that to, the dose per unit
length behind the shielding D where D Is the Integral value of the dose of
7DI 8
AW
gamma-radiation behind a slotted shielding; AM /is the distance along the shielding within
which the dome was measured) In introduced in order to. shad light on certain observed laws.;
A graph Is presented which ohms a oomparlson of the degreso,of weakening for different
2/5
Cwd
7

ACCESSION NR.- AT4019056
materials used to fill the slit (See Fig. 2. in the Enclosure). The ordinate shows the ratio
D /D (D is the specific dosage behind a continuous or unbroken shielding), while the density
Wthe material filling the slit (g/cm3) Is indicated along the abscissa. The result permits a
determination of the degree to which the shielding Is weakened by the presence of a slit
filled by any material, provided the dosage behind a continuous (unbroken) shielding (or behind
a slitted shielding for any singe slit material) Is known. This method and'certain variations
of Its application are analyzed., Orig: art. has: I formula and 6 figures.
I'ASSOC.U770K.- none A
BUBMUT D: 14Aug63 DATE ACQ.- 27Feb" ENCL: 02
SUB CoDut NP NO REF WWI 001 OTHER: 003
3/5
cmd
----- . . . . . . .

ACCZMO,N NRi AT4019056..
r2
nmrn~F-72
Figure 1.
Schematio dra~ffng of the device for moving Um a
ource: I r
- guides; 2 - rod with
source; 3 - brackets; 4 ---~ bearings;, 5 - SD-2 moton 6 & 7 - pulleys; 8 - shaft;
9 - coll; 10 - armature of elecitromagnetic oleffe; 11 - electromagnet; 12 - stand;--
C13 --owftchl-
4/5
Card

ACCZOSION KRt AT401i656 EvctoGms 02
dio
->00
00~
f
C'.0 0
00
-Its
~Y,tll;e& prosen ce of aalit as a func
Degree of weakening Dj/D of shielding Uon of the
specific gravity of the material used to fill the alit: 1 - lead shielding; 2 - stool
shielding; 0- calculated values for steel, oonareto and water; r - plo)dgl&Ga;
C - gTaphito jA- 1. 6 g/cm3)
Card

ACCESSION NR: AT4019060 S/0000/63/000/000/0260/0270
AUTI'011: Avaycv, V. N.; Vasillycv, G. A.; Yegorov, Yu. A.; Kuchcryayev, V. A.;
Y,
Orlov, Yu. V.; Pankratlyev, Yu. V.; Panov, o.
TITLE: Counters and dosimeters for the study of shielding and shielding properties of
materials
SOURCE: Voprosy* fiziki zashchity.~ reaktorov; sbornik statey (Problemi in physics of
reactor shielding, collection of articles). Moscow, Gosatomizdat, 1963, 2G0-270
TOPIC TAGS: counter, scintillation counter, dosimeter, shielding, reactor shielding,
nuclear reactor, gamma ray, neutron
ABSTRACT: In the study of the shielding properties of different materials and their com-
binations, it is important to know the following parameters: coefficients of attenuation of
r-ray and neutron streams of different energies; coefficients of attenuation of the power
level of r-radiation and fast neutorns; yield and spectrum of captured r-radiation; acti-
vation of materials in a neutrons flux; and deformation of tho X-ray and neutron spectra
in their passage through the material. Since existing equipment to insufficient for shielding
studies,' the authors built and tested a number of scintillation counters and dosimeters.
Card 1/3

ACCESSION NR: AT4019060
Among those described are a scintillation counter and spectrometer for the study of the
attenuation of 4?-ray flux, consisting of a FEU-11B photomultiplier with an N.-LI(TI) crystal
(diameter and height 40 mm) mounted in a housing lined with aluminum foil, and a
scintillation neutron counter consisting of a FEU-11B photomultiplier with plastic scin-
tillator of ZnS(Ag) + lucite (diameter 30, height 10 mm). For neutron energies ~ 2 ?VICV,
a alibrated with a Co6O source and eliminated by the proper bils
ther-ray back round is c.
In the analyzer. A similar neutron counter can be used as a monitor. A light guide In
conjunction with a smaller counter is used when the opening In the shielding Is too small.
This light guide is made of organic glass aength 60, diameter 10 mm) and is equipped with
a light collector (Tove, P. A. Rev. of Sci. Inst. 27, 143 (1956)). For neutron energies
between I and 10 Mev, a stilbene crystal is used (diameter 30, height 20 mm) equipped
with 'the (r-disc rim ffiation arrangement described by 11. W. broch (Rev. Sol Instr. 31,
1063 (1900)). The detection efficiency for neutrons between I and 10 Mov Is 10 - 2%. For
thermal neutron detection, a F BU-20 or FEU-31 photomultiplior with an L120- M02 I
g ass
scintillator is used. Detection is based on the reaction UG + n4 C~ + H3. The sensitivity
of these counters to rrays is calibrated by ZnG5 to CoGO sources. All-wavc-length neutron
counters are constructed as gas counters (type SN&INT-5) filled with BF3 and enclosed In
paraffin, which Is lined on the outside with cadmium, Dosimeters for fast neutrons are
Card 2/3

ACCESSION NR: AT40190GO
made from plastic scintillators (polystyrene + terphenyl + ROROR) attached to a FEU-25
photomultiplier. The pliotomultiplier current is integrated and amplified by a direct
current amplifier. The maximum sensitivity of this dosimeter to 0.2,u Flsec per division.
In ordcr to eliminate r-ray background, tho measurements are made simultaneously with
a e -ray dosimeter which Is a combination of tho plastic and Inorganic scintillators. A
cryst,,d of CsI(T1) (volume 1. 5 cm3) Is mounted on the axis of the plastic crystal (poly-
styrene + terphenyl + ROROR). Finally, a universal stand for detection and power supply
is described. "The authors thank V." M. Isakov, D. 1. Chupy*rin, A. I. Vasil 1yov,
V.N. ICozy*rov and Yu. G. Antsimov for taldng part In tho construction and adjustment of
the apparatus. 11 Orig. art. has: 9 figures and 1 tablo.
ASSOCIATION: none
SUBMITTED: 14Aug63 DATE ACQ: 27FCU4 ENCL: 00
SUB CODE: NP NO REF SOVi 615 OTHEIL 004

WN
J'ACCESSION NR: AT401906'1 S/.0000/63/000/000/0270/-0277
AUTHOR: Avayev, V. N.; Voskresensky, Ye. V.; Yegorov, Yu. A.; Orlov, Yu. V.
TITLE: Use of radioactive indicators In the investigation of shielding
SOURCE: Vorposy* fizild zashchity* reaktorov; sbornik statcy (Problems In physics of
reactor shielding; collection of articles). Moscow, Gosatomizdat, 1963, 270-277
TOPIC TAGS: nuclear reactor, reactor shielding, shielding evaluation, *radloactivo indicator
n
neutron detector, scintillation cou' ter, Gamma ray, neutron
ABSTRACT: The authors suggest that the efficiency of radioactive Indicators such as A127
InI15, 1127 or AuI97 can be increased by an improved method for detecting and
IV105,
counting they-rays, The advantages of using radioactive indicators as neutron detectors in
the study of shielding are: (1) the ability to detect neutrons which are either above certain
energy levels (threshold detectors) or within a certain energy Interval (resonance detectors);
(2) the smallness of the Indicators (can bo used without disturbing tbp distribution of the
neutron flux); (3) insensitivity to Y radiation-, and (4) ability to be us6d to estimate the neu-
tron energy spectrum. The disadvantages are their small effective cross section and the
relative insensitivity of the gas counters used in conjui~ction with the indicators to measure
the yradiation. in the present paper, in order to increase detection efficiency, a 4f/

ACCESSION NR: AT4019OG3
scintillation counter was used for cylindrically shaped radioactive indicators and a 2
scintillation counter for planar indicators. 4 ~1' scintillation counters consist of two 1)] oto-
multipliers of the FEU-43 type, each provided with a Cs1(T1) crystal 60 min in dinnicter and
.30 mm In height. 'Both crystals arc packed in one container and divided by an alumintim foil,
The mounting of the photomultiplier and associated equipment Is 6hown. The
ray efficiency
of the 4 lii' counter was near 100%. This allows the use of very small indicators (8 min in di-
ameter and 5-50 mm In height) for cylindrical specimens, the wall thickness of which can b,~
0. 1-0. 3 mm. Cylindrical indicators are mounted in a lucite tube (9 mm in diam.) with a
wall thickness of 0. 5 mm. With the use of cadmium or boron-cadmium filters, the total
diameter is between 15 and 32 mm. Plam.- indicators are deposited on a lucite substrate,
1 mm. thick. Tile dimensions of the indicaiors are from 5 x 5 to 40 x 40 mm. with a thickness
of 0. 1-4 mm. FEU-41 multipliers are used with NaI(TI) crystals (diameter and height 40
mm) for planar indicators.' In order to eliminate they-ray background, a single--channcl
analysis system was used. The best technique Is to dbunt not the Integral number of pulses,
but the most intenseT line or group of *&nes, characteristic for a given indicator. The
ray energies and characteristic reactions for the most common indicators are tabulated.
1his method improves signal to noise ratio and eliminates the necessity of very pure ma-
terials. An example of how the use of this method enables one to oliminato the influence cf
L.Card

,!ACCESSION NR: AT4019061
thermal and epithermal neutrons In the detection of fast neutrons by a radioaluminum Indicator
Is shown. "The authors thank D. L Chupy*rIn for assembling and adjusting the electronic
apparatus and N. Ye. Vasin for designing the 4'j? -counter. Orig. art. has: 6 figures and
table.
ASSOCIATION: none
SUMUTTED; 14Aug63 DATE ACQ: 27Feb64 ENCL: 00
SUB CODE: NP NO REF SOV; 004 OTHER: 002
Crd 3/3

ACCESSION NR; ATW9063' 'sloooo/63/000/000/0281/0289
AUTHOR: Avayev, V. No; Yegorov, Yu" A.; Orlov, Yu. V.
TITLE: Computation of-, t*he c ri~ierlstlcs of gamma-radiation and fast neutron
spectrometers by the random test method
SOURCE: Voprosy* fIzIkI zashchity*.reaktorov; sbornlk statey (Problems In phyilcs
of reactor shielding; collection of articles). Moscow, Gosatomlzdat, 1963, 281-289
TOPIC TAGS: nuclear reactor, reactor shielding, radiation-spectrum, neutron
scattering, radiation dosimetry, neutron, Gamma ray, scintillation spectrometer,
crystal spectrometer, random test method, Monte Carlo method
ABSTRACT; The authors note that the most convenient devices for the study of
continuous Y -radiation and neutron spectra are ;~"-radiatlon scintillation spectro-,
meters with complete absorption of the Y-quanta energy, that Is, spectrometers
with a large-size scintillator, and also fasi-neutron spectrometers with one
sensor. The relative advantages and disadvantages of these types are discussed
and the preference Is accorded to spectrometers with large crystals. Processing
of the test results obtained with these spectrometers Is-possible provided one
knows the forms of the Instrument lines of the monochromatic radtations at a-numbe~,
of energy values and the dependence of the efficiency an the energy of the gamma-
Card -J /4_.--7"

ACCESSION NR: AT4019061
-spectro-,
radiation and neutrons. it is.pointed out that for a scintillation gamma
meter In a gamma-quanta energy range of approximately 100 kev to 3 Mev, the form o
the Instrument line and the efficiency.can be determined experimentally by measur-
In th gammamapectra of radioactive sources of Y-radiation (Ce141, Hg203, Cs137,
;5 en
Zr , Z 5., W4, and others), but that for higher gamma-radiation energy levels
and fast-heutron energies the experimental determination of the efficlenqy and
the form of the line Involve great difficulties. These values may be calculat d
In the case of both spectrometer types by the random test method (otherwise known
as the Monte Carlo method). in the present article, a system for spectrometer
characteristic computation by this method is considered. For the sake of simpli-
fying the exposition, In both cases a plane problem Is solved; that Is, the
authors consider that all processes of scattering and absorption occur In the xy
plane. The authors note that the solution of the spatial problem does not differ
essentially from that of the ptane problem. The paper Is In two sections: In the
first-the problem of the computation of the characteristics of a gamma-spectro-
meter Is discussed; In the second - the computation of the characteristics of a
neutron spectrometer r In the first case, the movement of the r-quanta of the
source In the scintillator and the movement-of the products of Its scattering are J
sequentially examined until either they are absorbed In the crystal or fall out-
ilde Its limits. For each ty-quantum of the source, a determination Is made of
Card 2/4

I'ACCESSION NR: AT4019063
the portion of the energy which Is'expended on Ionization as a result of secondary
processes. This computation Is repeated for a large number of source -quanta.
The results thus obtained are used to construct rated spectra histograms (fre-
quency polygons) which define the resolution of the spectrometer (without consider-!
ation of the physical resolution determined by the resolving power of the.scintil- I'
.1ator and photomuitiplier). A comparison of the number'of "absorbed" gamma-quanta 1
w[th the number of those considered determines the efficiency of the spectrometer. !1
In the second section of the article, a general description of the physical com-
position and operational principle of this type of Instrument Is given. The problem
of the time lag between the moment of formation of the proton pulse and the pulse
from the alpha-particle is discussed. The determination of the efficiency and -
resolution of a fast-neutron scintillation spectrometer, and also a rationa
selection of the delay time, requires the solution of a problem, formuipced by the
authors In the following terms: Incident to and along the axis of a cylindrical I
scintMator, the composition of which contains hydrogen, carbon, oxygen and boron 11
atoms, Is a stream of neutrons having an energy EO; It Is necessary to find the
time to from the moment of the first scattering In the hydrogen to the moment of
the capture of the neutron by the boron nucieus,'to datirmIne what part of-Its.
energy the neutron has lost as a result of scattering on the hydrogen nuclei, and
to find the ratlo'nbtnot where no Is the stream of source neutronsp and nb Is the
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ACCESSION NR: AT019063
number of neutrons captured by the boron after scattering in the hydrogen. Since
the scattering sections of the neutrons by the hydrogen and carbon nuclei are
large in comparison with the capture sections,-and the capture section of the boron
nuclei Is great In comparison witb the scattering section, It may be assumed that
the hydrogen and carbon nuclei only scatter the neutrons, while the boron nuclei
only absorb them. At the time, scattering and absorption by the oxygen nuclei may
be disregarded, since the full section of the oxygen is small In comparison with
the sections of hydrogen, carbon and boron. In both sections of the paper, the
authors discuss the pqssible use of electronic computers In carrying out the
calculations by the.formulas derlved. ."The authors express thanks to V. N. lgnaten,-
ko for carrying out the calculations". Orig..art. has.*' 9 -figures and 17 formulas.1
ASSOCIATION: None
SUBMITTED-' IIIAU963 DATE.ACQ: 27Feb64 ENCL: 00
OTHER: 005,
SUB CODC: lip NO REF SOV! 003
Card 4/4

ACCESSION'NR: AT4012064 S/0000/63/000/000/0289/0303
AUT11OR: Avayev, V. N.,'Yegorov, Yu*. A.,,'Orl6v, Yu. V. Frolov, A. S. , Chentsov, -No No
TITLE: Computation and analysis of the chatacteristics of a-spectrometer with a.boron-,
hydrogen scintillator
ki zashchity* reaktorov;'sbornik statcy (Problems In physics of
SOURCE: Voprovy* fizi]
xeactor shielding; collection of articles). Moscow, Gosatomizdat, 1963, 289-303
iTOPIC TAGS: nuclear reactor, rcactQr shielding, spectrometer efficiency, xylene borato'
4scintillator, phonylcyclohexane borato scintillator, radiation dosimetryo scintillation
spectrometer, boron hydrogen sciptillator, neutron energy, yield nucleus method, twin
sensor spectrometer, neutron spectrometer
* p
ABSTRACT: Among the methods for .determining the energy of f"t'neutrons, the authors
call articular attention to the yield nucleus method, noting that a special position in this
method is occupied by scintillation.spectromoters. Twin-sensorfast-noutron spectrometers'..--
are described and their operational principles are briefly analyzed. It Is pointed out that
fast-neutron spectrometers with two sensors can operate only with collimation of the neutron
The HmMtlons imposed by this circumstance, particularly with reference to the
study of fast-neutron spectra behind shielding, 9~re noted. The subject of spootrometers j
Card
art

ACCESSION NR: AT4019064
with one hydrogen-containing sensor to introduced. The discriminatidn of the gaffima-back-.
1
6-round in these spectrometers is accomplished through the difference In the glow time of
:the scintillator when excited by. protons and electrong . It Is further noted that spectro-
pable of operating without a collima
meters with a single hydrogen-containing sensor are ca
tion device. 'The lower boundai7y of the measured no4tron energy levels is normally not less
thaA 0.- 7 Mov. While such instruments have been usc4 for a wide va~lcty of test purposes,
the author observes that spectrometers with a hydrogon-containing sensor cannot be used
for measurements against a high gamma-background.. The singlo-sensor scintillation
spectrometer, the scintillator of which contains hydrogen and boron, and which was proposed
by Marshall M-" nor. Phys. Soo. 27, 11 (1952)), is described in detail and its ad-
vantages ar., -zal,' j.' It is noted, however, that the data necessary to permit ihe actual
construction of I su. a spectrometer are lacking inthe available technical literature. The
following values particular, are unknown: 1) the 'efficiency of the specirorActer as a
function of the enz rv of the neutrons; 2) the efficiency as a function of the yolume of the
**o of the hydrogen and boron concontratiops in It; 3) the timd distribu-,
scintillator and the iL
'tion of the pulses from. he alpha-particles (with the time read from the moment of the first'
scattering of the neutron); 4) the energy resolution of the spectrometer as a function of the
energy of the neutrons. Noting that attempts haw been made to stj%~y this lacking Informa~-)
w
tion manually by means of the Monte Carlo method, the results of w oh have made it
2/6
Card

i.ACCESSION NR; AT4019064
possible to draw corwn useful conclusions leading to an inittatfon of work on the design of
a spectrometer, the author cafla attentloh to the failure of the manual method of calculation
to piovide a completo'picture of the required characteristics, and the great ambunt of time
such computation techniques necessarily consume. The present article, therefore, reports
dcUiled computations of the characteristics of a boron-hydrogen scintillation-type spectre- I
motor, conducted with the. aid'6f an electronic computer. In Individual sections of the paper
the author discusses tho,formulation of the problem, the actual computation of the speciro-
meter characteristics, the fundamental block-diagiam of the program used to carry out tho
spectrometer characteristic computation described in the article and, finally, vin analysis
of the results of the computation, on the basis of which all the laws characteristic of a
spectrometer with a boron-hydrogen scintillator are explained. The author learned, among
other things, that: 1) Spectrometer efficiency as a func%lon of the resolving time of the I
il Oincidence circuit has a maximum value, the position of which (on the various graphs and
curves plotted in the article) is different for scintillators of different dimensions and com-
position; 2) Spectrometer efficiency is directly proportional to the concentration of boron ,
nuclei: 3) The efficiency maximum Is-moro distinctly expressed for scintillators with'a
higher concentration of boron ndclel; 4) The efficiency maximum Is less clearly expressed
for large volume scintillators: 5) The efficiency maximum is less clearly expressed for a
[cylindrical scintillator than for a spherical one with idenUcal diameters of the sphere.and
3/5

09
ACCESSION NR: AT4019064
cylinder base, and is shif iod t'h the direction of greak coi ncldcjico Arcult resolving time.
9
The results of the computation' and analysis of the chFactoristics of'a sci4illation
spectrometer with a boron-h0rogon scintillator shokd that, of all ~o co,inpositions,
considered, the most suitabl6 is a mixture of equal-~arts of xylono ( lmethylbenz-..-,,--
ihyl borate with boron ~10 enriched tc 96%, ' ured into a
phenyleyclohexane with trime Ro
vessel 80 mm in both diam.eter and height. The resolving time of thq coincidence circuit
in this case should be equiLl to approximately 1. 5 midroseconds. On~'the basis 6f the study,
the block-diagram of the spectrometer shown in -Figure I of the Enclo'sure~ was adopted for
development. In order to reduce the number of random coincidences, a Bingle-channel pulse
amplitude inalyzer was introduced into the spectrometer control circuit. Orig,' art. has:
11 figurei and 13 formulas.
ASSOCIATION: None
J SUBAUTTED: 14Aug63 DATE ACQ: 27Feb6.4 ENCL: 01
S'
U13 CODE: NPj OP NO REF SOV: 010 OTHEM 008
a 4/5
~j-
C

ACCESSION NR: AT4010OG4 ENCWSURE.' 01
2 3 4 5 12
7
6 .7 7 10
14 13
Fig. l'-- Proposed block diagram-of a b'oron-hydrogen scintillation spectrometer:
1) C - scintillator, 2) K 11 - cathode follower; 3)jjj~ photomultiplier;
4) r7yc - preamplifter; 5) Ye - amplifier; 6) J?Yc - linear ampl1frar.
7)r,3- delay line; 8) CC - coincidence circuit; 9) ~~ - blocking unit;
10) K - electronic key; .11) OA - single-channel pulse amplitude analyzer;
12) PO - regulating monovibrator; 13) 0 - limiter; 14) AA - multichannel,
pulse amplitude analyzer.
Card 5/5
TP

!ACCESSION NR: AT4019066 6/0000/63/000/000/0304/0310
Yu. A.; Pankratlyev, Yu. V.
;,AUTHOR:
TITLE: A single-crystal fast-neutron spectrometer for the measurement of continuous
qmctra
SOURCE: Voprosy* fizild zashchity* reaktorov; sbornik statey (Problems In physics ~f
i
reactor shielding.- collection of articles). Moscow, Gosatomizdat, 1963, 304-310
TOPIC TAGS: nuclear reactor, reactor shieldin; yield proton method, stilbene scintillator, x .'i
radiation dosimetry, neutron, neutron spectrometer, single crystal spectrometer, continuous
spectrum, scintillation spectrometer, organic scintillator
ABSTRACT: The authors call attention -to the differences between spectrometers with a
single hydrogen- containing scintillator and other high-efficiency scintillation spectrometers.A
It to pointed out that the possibility of discovering differences In the glow time of certain
,orgwiic scintillators when: they are radiated by protons and electrons and the development of
methods for the discrimination of pulses caused by gamma-radiation has recently made
possible a far wider application of single-crystal spectrometers for various kinds -of measure-
ments. The yield pr9ton method Is discussed as the most widely used technique for the
Card 1/6

ACCESSION NR: AT4019065
measurement of the energy values of fast neutrons in connection with the spectrometer
type under consideration. Formulas are obtained for the number of yield protons for given
scintillator parameters and in a given energy range. An additional formula Is given whereby
the correction factor for secondary scattering and yield proton energy leak (dissipation) can,
be calculated. A spectrometer designed for measurements In a nuclear reactor is described.
Crystal thickness as influenced by the presence of an Intensive gamma-background is con- I
sidered In some detail. A graph Illustrating the correction factor for secondary scattering
and for Incomplete proton energy absorption Is presented. Ile authors claim that, depending
on the neutron energy, the efficiency of the 5-mm thick stilbene crystal used in the
spectrometer described varies from 371 f6rE =2Mevtol.3%forE =10Mev.ulsfurtheri
claimed that no other fast-neutron scintillaJon spectrometer posseRses such high efficienicyl
An FEU-33 photomultipliei is used In the single-crystal spectrometer. A discrimination
circuit proposed by Brooks (Nucl. Instrum, 4, 3 (1059)) Is employed to eliminate the effect
of the gamma-background. A block diagram of the device used to balance this discrimination
circuit In given in the article. By means of this circuit, eaelf pulse on the oscilloscope
Screen In represented by a gleaming dot. A block diagram of the Bingle-orystal fist-neutron
:,Card 2/6

!ACCESSION NR: AT4019065
[spectrometer may be seen In the Enclosure. A pulse, whose amplitude is proportional to
the yield proton energy, Is tapped from the photomultiplier diode and passes throug the
cathode follower to the linear pulse amplifier. The boosted pulse Is fed through the delay
line to the electronic key. For control of the operation of the ape ctrometer, a pulse from
the output of the discrimination circuit Is used which passes through the cathode follower to
the amplifier, and then to the integral discriminator. This Integral discriminator is at the
same time a regulating mono-vibr iator and is so tuned that It Is trIggered'only by proton
pulses. For pulse amplification in both spectrometer channels type USH-10 amplifiers are
used. The pulse amplitude analyzer Is a hundred-channel analyzer, type AI-100-1. - The
techniques used to check the quality of the spectrometer operation are described in the
article. Control measurements indicated that operation was reliable. In the region of
neutron energy values greater than'O. 9 Mov, the test results lend themselves to easy pro-
cessing (the tests were conducted by measuring the neutron spectra of Po + Be, Po + B
sources, a nuclear reactor and the spectral deformation of a Po + Be source in water).
The apectromet~r was found to ~f practically insensitive to gamma-radiation In a stream of,
gamma-quanta approximately 10 greater than the neutron stream. "The,authors wish to
thank Yu. G. Anisimov for his assistance in conducting the experiments and In calibrating'
the spectrometer. Orig. art. has: 7 figures and 7 formulas.
CordS15

Card 4/5

ACCZMOK NR: AT4019066 ENCLOSURE:'01
3 4 6
ilyc
6, 9
6. 9
Oor x
YC
.4
3 7 8
Figure 1. Block diagram of the single-cMtal fastneutron spectrometer: 1 - radiation source;
2 - spectrometer sensor with discrimination circuit; 3 - cathode follower; 4 - linear
pulse amplifier; 6 - delay line; 6 - electronic key; 7 - anipliffer; 8 - Integral die-
tor; 9 - pulse amplitude analyzer
Card 5/6

ACCESSION NR.- ATWI9066 S/0000/63/000/000/0310/0312.
AUTHOR: Yegorov, Yu. A.; Orlov, Yu. V.; Pankratlyev, Yu, V.
TITLE: Permissible Gamma-background In measurements by a fast neutron spectro-
:1 meter with a single detector
In fth~_
sics of reactor shielding; collection of articles). Moscow, Gosatomizdat, 1963t
310-312
TOPIC TAGS: neutron spectrum, Gamma-background, fast neutron, reactor shielding,
spectrometer, spectrometer discrimination, photomultiplier, neut.ron flux measure-
ment
ABSTRACT: The discriminatin ability of a single-deteetor fast neutron scintilla
tion spectrometer against a ~ -radiation background wasstudied by two methods;.
separation by an electronic circuit (Brooks, F, D. Nucl.~Instrum. 4, 151 (1959))t
and separation based on the spatial charge saturation 1w .Ithe region between the
last dynode and the anode of a photomultip)ier wen, R& B. Trans. I.R.E& PGNS
(0
5, 198 (1958)). In both cases, an FEU-33 photomultiplier was used with a stil-
bene crystal DOX20 mm). The energy threshold of the spectrometer was set at
6 ev and determined from the reaction D(d,n)Hdo A Po + Be neutron"source was
r

ACCESSION'NR:"'AT4019066
used and Co60 served as a Y-radiation source. The results are given in the
Enclosure, based on data obtained by the electronic circuit separation method
(Fig. la).and the spatial charge saturation method (Fig-.1b), respectively.
As seen from Fig. la, Y-quanta at 1.33 Mev are not registered until the intensi-
ty of r radiation exceeds 4mc/sec. In the spatial charge saturation method,
-quanta are registered only,if the limit of 15-20 mc/sec Is exceeded. It is
found, however, that Yradiation with energies greater than 3 Mev is registered
when the spatial charge saturation method is used In measurements on a nuclear
reactor. This difficulty is avoided by increasihg,the energy threshold to 2.1 MeV
It Is then possible to measure a'faLst neutron spectrum when the ratio of neutron'
flux to that of Orig~_art. has:. 2 figures.
r-rays is 1:2000.
ASSOCIATION: none
DATE ACQ: 27Feb64 ENCL: 01
14Aug63
I SUB CODE: NP NO REF SOV: 005 OTHER: 003
;cicrrd -:,2
I --------
MAR
-A bawl
_V,

ACCESSION.URt AT4019066 ENCLOSUREt 01
I A
4
f- 68 f# 20
a b
Reco~dlng characteristics of a fast neutron spectrometer wl-th a system'of
discrimination based on: a) comparing the full charge count with the peak
count electronically; b) the Y-background of the spatial charges In both
.a and b: ordinate relative number of counts, and abscissa radiation
dose - In PO/sei.
IN OT
Z~ N-

t 8128-66 -EWT(m) L-EWP(J)/t RM
A
so
AP5025020 SOURCE CODEt UR/0286 5/000/016/0080/00
q
AUTHORS: Muromova. R.-SA'Pletneva,L D.j,Dq1.dqvaT. Vo; regorov, Yu. A. s 44
Pervukhina, I. V.; S ......... ...
)ikhj~mnta 1. V.
ORG: none Ij
u'4
TITLE: Method for obtaining p0lyumidesA Class 39, No. 17392.9 fannounced Q!i!!t-8
Scientific Research and Develo ute of th Nitrogen IndusM and Products
ETnt Instit
azotnoy promyshlen-n-os-ti produktov organicheskogo sinteza)-7
SOURCE: Byulleten' izobreteniy i tovarrykh znakov, no. 16,, 1965, 80
TOPIC TAGS: polymer, polymerizationp polyamide, a7d" cycloheVl alkane acidp Isomer
ABSTRACTs This Author Certificate presontsa method for obtaining polyamides on the
basis of amino-cyclobezy1alkans acids, ease the mechanical strength and
stability of the polyamides and fibers(dTA-Wd from them, the ois-isomers of R~
( 3 -aminocyclobeVl) propionic-a-n-U-76'- ( 3 -aminocyclohexyl) butyric acids and
their mixtures with other polyawido-forming compounds are usa4 as starting materials,
SUB CODE; OC/ SUBM UTE: 22Apr63
UDG.s 678,675
-A

YEGOROV, Yu.A.; YAKUBOV, N.T.; KATORZI,.'NOV, N.D.
Manufacture of pip6~ with a small Jlnzeter. Khim. volok.
no.4s67-68 164. (MIRA 18:4)
1. Vsesoy-uznrf naltf-,I--nr-i-r~slf-,dovatellskiy li,ntLtut isk,13Stvennogo
volokna.

'ACCESSION NR: S/Cooo/63/000/000/0312/0318
AT4019067
IAUTNOR: Avayev, V. N.; Yegorov,.Yu. A.; Orlov, Yu- V-
TITLE3 Gamma pair spectrometer
SOURCEs Voprosy* fIzIkI zashchity* reaktorov; sbornik statey (Problems in physics
of reactor shielding; collection of articles). Moscow,.Gosatomizdat, 1963, 312-318
TOPIC TAGS: nuclear reactor,'reactor shielding, radiation dosimetry, spcctrometerol.
Gamma spectrometer, Gamma pair spectrometer, scintillation pair spectrometer,
electron position pair, annihilation radiation
ABSTRACT: The authors describe-a scintillation-type gamma-pair spectrometer which
Is being successfully used to measure the deformation of the Y-spectra of a,
nuclear reactor In the shielding In the region of Y-quanta energies greater than
1,5 Mev and for the study of capture Y-radtation. When the energy of the gamma-
quanta Is absorbed by the material of the scintillator, annihilation Y-radiation
Is generated as a result of the formation of the electron - position pair, result-
Ing In.iwo jl-quanta, each with an energy of 0.51 Mev. If the dimensions of the
scintillator are small, the annihilation V-quanta leave It. In the scintillator,
meanwhi I a, energy E Eyo - 1.02 Mev I s absorbed. Thl s c1 rcumstance, makes 'I t
-card- 1/5-
a M'.
- - - - - --- - - - -

ACCESS ION NR: AT4019067
possible to construct a scintillation pair spectrometer which will compare favor.
ably with.spectrometers of other types, The spectrometer circuit Is so designed
that only the amplitude of those pulses Is measured which are caused by the ab-
sorption of r-quanta energy resulting from the process of pair formation. For
this purpose, the spectrometer sensor Includes, In addition to the scintillator
radiated by the Y-quanta stream of the source, two supplementary scintillators to
record the annihilation )(-quanta. Further theoretical considerations are explain-
ed In the article. The advantages of a scintillation gamma pair spectrometer dis-
tinguish It favorably from ar-spectrometers of other types and particularly from
single-scintillator spectrometers, even If the sclntillator is large In size. The
difficulties generally encountered In deciphering the results of measurements of
complex jr-spectra by means of a spectrometer with a scintillator are discussed In
some detail. The point is emphasized that the pair spectrometer Is practically
Insensitive to-fast neutrons. This Important advantage of the scintillation pair
spectrometer is particularly valuabI6, if the spectrometer Is employed to measure
Y-spectra in the presence of a,neutron background - for example, in 'nuclear
reactors. Two defects are also mentioned: 1) the efficiency of the spectrometer
Is not great, but In order of magnitude lies between the efficiency of a single-
ScIntillator spectrometer and a Compton s_pectrometer; 2) the electronic circuitry
Is extremely complex. A block diagram of the scintillation gamma pair spectro- I
Card 2/5

ACCESSION NR: AT4019067
meter discussed In this article may be seen in the Enclosure. The principle of
operation is explained thoroughly In the article* As a central sensor, a
spectrometric photomultlpller, type FEU-42, has been used, mounted on which there
Is a spectrometric Nal(TI) crystal, 40 mm In both diameter and height. in the
supplementary sensors, type FEU-43 photomultipliers, with CsI(TI) crystals, 60
mm In diameter and 30 mm In height, have been used. The amplitude analyzer em-
ployed ls~a 100-channel analyzer, type Al-100-1, while standard slnqle~-channel
analyzers, type AADO-I, have been-placed In the control channel of the spectro-
meter for sampling pulses of specific amplitude. -Results 9f various tests Zon-
ducted with the spectrometer are presented and evaluated In the text. In parti-
cular, a test of the sensitivity of the gamma pair spectrometer to neutrons showed%,
the following: 1) in the energy region of Y-quanta approximately less than 2.5
Mev, some distortion of the gamma-spectrum Is possible (however, not more than
10%) which can be eliminated by means of additional measurements with a 100-mnt
thick bismuth filter; 2) If the ratio of neutron and gamma-quanta streams Is
approximately equal to unity, practically no distortions of the gamma-spectrum
are obs*erved; 3)*In the case of a gamma-quanta energy value above 2.5 Mev, dis-
tortions of the Y-spectrum by the neutron background are likewise not observed.
A formula Is given for the computation of the efficiency of the spectrometer
for a quantltatlve estimate of the ratios In the gamma-spectrum& Orige art. has:
d"figms.

.m
f
I
I
i
i .
;. -
. -t ~~
I ,;., -,., . .
,7 :, - . ,

Acassiow us AT4019067 UNCLOSUREs 01
A E G M
E G D
C 0 D N
fig. 1. Block diagram of the r-pair spectrometer:
A - central sensor of the spectrometer; 8 and C -
supplementary lateral censors; 0 - cathode followers;
E - single-channel amplitude analyzers;*F - linear
pulse -Onolifler; G - shaping blocks; H and L - delay
lines; I and J--; coincidence circuits; K - electronic
key; M - discriminator-limiter; 100-channel
amplitude analyzer
Cai4, 5/5
--------------
I MUM-W-MIN=

8/0000/63/000/000/0319/0327
ACCESSION NR: AT4019068
AUT1101i: Yegorov, Yu. A.; Orlov Yu. V.
TITLE: Use of a single crystal Gamma spectrometer for measurements on a nuclear
reactor
SOURCE: Voprosy* fiziki zashchity* reaktorov-, sbornik statey (Problems In physics of
reactor shielding; collection of articles). Moscow, Gosatomazdat, 1963, 319-327
TOPIC TAGS: nuclear reactor, reactor shielding, spectrometer, Gamma spectrometer,
single crystal spectrometer, Gamma ray, sodium Iodide, cesium Iodide
ABSTRACT: The absorption and amplitude distribution of Y-rays from various sources I~
the energy region from 0-10 Mev wag; studied with Nal(TI) and CSI(T1) single crystal
spectrometers. It is pointed out that "total absorption" of j(-rays by a crystal Is a relative
concept due to the finite size of the crystal. Thus, the amplitude distribution of Yradiation
consists of-, a) a peak corresponding to the total absorption, and b) a continuous background
due to the partial absorption. The dogroo of absorption completeness Is determined by
the magnitude of photofraction, I.e. the ratio of the area under the peak to that of a con-
tinuous distribution. It is found, in agreement with previous measurements (W. F. Miller
1/4
Card---
JR2 IM-TYMI
7

ACCESSIONNR: AT4019068
andW. J. Snow, Rev. Scient. Instrum. 31, 49, 1960), that the magnitude of photofraction
shows an initial sharp decrease with Increasing energy of the X rays and then remains
constant. The magnitude of photofraction was studied for single crystals of N1I(T1)
(125 x 100 mm) and CSI(T1) (80-90 x 80-90 mm). The results are plotted in terms of the
number of impulses per channel vs. the channel number. Due to the larger coefficient of
absorption for T-rays In the CSI(T1) crystal, the magnitude of photofraction was increased.
Ile crystal efficiency vs. Y-ray energy is also plotted for these crystals. Tt is shown that
the neutron background around a reactor can be eliminated by placing a bismuth filter of
I sufficient thickness for the total absorption of the )r-rays in front of the detector. In the
presence of a neutron background, the number of Y-rays registered In each channel can
be determined from the relation JV-,=JV-I.3JVB,, where N Is the total number register-.
ed In a channel without a filter and NBi Is the number In the presence of a filter. The
Y-ray spectrum from the active zone of a water reactor as measured by a C.%(TI) crystal
is given in Fig. I of the Enclosure. The amplitude distribution spectra of r -rays from
various sources indicate that spectrometers based on Nar(TI) and CSI(TI) single crystals A
can conveniently be used to measure the radiation escaping from the active zone of a
reactor. Orig. art. has: 11 figures and I formula.
ASSOCIATION: None
2/4
!.!;ard
Fli:4

ACCESSION NR: AT4019068
SUBMITTED: 14Aug63
SUB CODE: NP
DATE ACQ: 27Feb64
ITO REF SOV: 005
ENCL- 01
OTHER; 003
'a"

ACCESSION NR: AT4019068
>
CU
Q
!102
0
0
C;
z
2
ENCDDSURE: 01
of
Y
the
energy
-rays in Mov.
Fig. I - Gamma spectrum, (amplitudes distribution of' Y -rays escaping from the
activ6*zbne* of a.reactor through a 1-m water layer, measured by means
of a CSI(TI) crystal (80 x 80 mm) spectrometer.
Card 4/4

BRODER, Dmitriy Leonidovich, doktor fiz.-mat. nauk; POPKOV,
Konstantin Konstantinovich; RUBANOV, Stanislav
Mikhaylovich; GLADKOV, G.A.p kand. fiz.-cat. nauk,
retsenzent; VESELKIN, A.P.p kand. fiz.-mat. nauk,
kand. fiz.
rotaenzent;.,jEGQIjff,_ju , -mat.nauk.
retsonzont; POLOGIKII, B.G., kand. fiz.-mat. naukj ro
retsenzent; VLASOVA, Z.V., rod.; CHISITAKOVA, R.K.,
tekhn. red.
[Biological shielding for ship reactors) Biologicheskaia,
zashchita st
~dovykh reaktorov. Leningrad, Izd-vo, "Sudo-
stroenie,1"1964. 410 p. (MIRA 17:4)

A t.D f fa,
-1 C;S, ras, rleu*r--,, --pectrurn. Ireactor V,
L I
rea;-!- protection
spectrum. neutron

and tables. "The authors are grateful to A. L, Barinov for his participation in
17,-1. An s,--nov, V. N. K c~ zv* r to v an dV. Rucb'ev
7i i4
SUB CODE: ITP NO RE F SOV: 008 OTHER: 008

S/0089/64/oi6/004/0355/0356
ACCESSION NR: 04029699
1 AUTHORS: Avayev, V. N.; Y~go~ovj A.; Moiseyev) G. G.
TITLE: Attenuation of neutron with an energy'exceeding 1.5 M'ev in
iron
SOURCE: Atomnaya pnergiya) v. 16, no. 4, 1964, 355-356
TOPIC TAGS: fast neutron, relaxation length, threshold energy,
semiinfinite- geoinetryg indium indicator, inelastic scattering,
water moderated re~ctorj fission spectrum
ABSTRACT: A study of the penetration of fast neutrons through irbn
involved the determination of the relaxation lengths N for neutrons
with an energy greater than 2 Mev. It may be assumed that as the
energy of the fast neutrons approaches the threshold energy (where
inelastic iron-nuclei scattering begins), the relaxation lengths of
the fast neutrons should increase. The spatial distribution of
neutrons with an energy greater than 1.5 Mov in iron was therefore
measured in a water-moderated, water-cooled research reactor in
conditions of a "semiinfinite" geometry. The neutrons were recorded::
-Card.-

ACCESSION NR: AP4029699
by an indium indicator Ereaction In (nj n') Inm3. The reaction thres-~
hold is somewhat reduced with the increasing thickness of the iron
layer due to the attenuation of the neutrons spectrum. The absolute
values of the relaxation length are somewhat higher than indicated
by the calculations, which is probably due to the differences in the 1
geometries of the experiments. The increasing relaxation length
with the growing thickness of the iron layer may be explained by the
accumulation of neutrons in the iron with an energy close to the
energy threshold of the inelastic iron nuclei-neutron scattering.
This was verified under the same conditions by measuring the spatial
distribution of neutrons in iron with threshold indicators made of
3 Mev) and aluminum (E
phosphorus (E
thresh.27 7 thresh. Mov). thresh. 5 Mev, and
Orig. art. ha : 1 table.
ASSOCIATION; None
SUBMITTED: lqJul63
DATE ACQ: OlMay64
ENCL: 00
SUB CODE: PH, NS
NR REF SOV: 004
OTHER: 003
2/-2'
Card_

L 2370-66 kWr(l)/FPC~114A(h) q.4
ACCESSION NR: AP5021010 UR/0203/65/W5/004/0794/0786
550-388.2
AUTHORSt AfEywo ich Y!g Yu. A,
TITLE: A device for mass inputrinto a digital computer of coordinates of experi-
mental curves, chosen for plots with a high*orror level
SOURCti Geomagnotism i aeronomiyu, v. 5, no. 4t 1965p 784-786
TOPIC TAGS: information storage, information retrieval, digital recording oyat
computer, ion distribution
ABSTRACT: A description is given for a means of introducing~ronogram r9p_rqs_Qp_t&-_
--tio into a digital computing machine. The method circumvents the time-consuming
task of introducing such data manually and also avoids the complexity and limita-
tion inherent in some earlier automated methods. The proposed device consists of
an optical system for projecting an image at a nolocted scale onto a screen
equipped with a push-button control for changing photo frames. The device also
features a photomecHanical coding system with simple electrical circuitry. The
screen Is ouch that each point on its surface In identified in a coordinate
system by moans of two binary numbers. The points along an arbitrary curve with-
in the referenno system may be digitized by means of moving an indicator arrow
fCard :..1/2--

-L 2370-66.
ACCESSION NR: AP5021010
along the locus of the curve, The arrow Is constrained to move In the plane of
the screon; the coordinates of the tip of the arrow are stored in a coro memory
unit whenever a contact switch is closed. The amount of diaitization ib at the
discretion of the operator., and the interpretation of multivalued curves is also
loft to the judgment of the oporatorp thus conserving atorago and removing the
work of qualitative dooiaion from the computer operation, A disounsion-of the
comparative worth of the proposed system Is given. Some areas of application
mentioned are: ana3,vsls of experimental curve plots, oeoillograms, particle
1. streaw , topographic charts, iaoline charts, eta. The use of an intermediate
information buffer would anowexpansion of the devicela capacity. The authors
thank MY,_Rj&:L4 for his constant attention to the .work,, Orig, art... hasi 1,
figure,
ASSOCIATION: Akademiya nauk,, KazSSR, sector ionoofery (ActkjtW ~f Soienqoy
KazSSR, Ionosphere Dapartmant)
-SUBMITTED: 17Sop64 sub-. COLE 1---DP ES
NO REF SM 004 OTHER: 000
6 V/<
Card_2/2
Y'~

A ('(7 F q q I ON T? PAP5005802 s GG87 !6 5 110 1 R IGO, "Id !2 1fol?T
SOUPCE, Atomnaya enerplya. V. 18. no. 2, 1965, 121-127
Tl 1! teriRtirs -f f-cnicretp ('ienri v
C

ASFOCIATIOU: none
SUSHITTED, 2 IFeb64
NO REF SoVt 012
card
ENCL! 00
OTHERS 001
SUB CODE: N px, r
ATD pREss 3180

5-66
L 1159 EW1(m)/E1FF(n)-2/DrA (h)
-------------
ACCESSION NR: AT5023145 UR/2692/65/000/004/0015/0030
Y,
AUTHOR: LvMSv, V. ' N.
TITLE:'Method for measurement of neutron sF�ctra in the epithermal energy re-
gion using resonance indicators
SOURCE: Moscow. Inzhenerno-fi ch jy
_tnqtjt.Rt,,.Yoprosy dozimetril I zash-
chity ot izlucheniy, no. 4, 1965, 15-30
TOPIC TAGS: neutron spectrum, nuclear resonance, radiation dosimetry,
cobalt, aluminum, tungsten, indium, gold
ABSTRACT: In the. present work, 13 indicators were selected making possible a
calculation of the contribution of the 1/v neutron spectra in the energy interval
from 0. 46 electron volts to 6 thousand electron volts. There Is considered the
possibility of determining unknown spectra by comparison with the I/E spectrum.
The absolute values of the neutron flux are found by measurements with gold
indicators whose activity to determined absolutely. The article gives a mathema-
tical description of a method for measuring the neutron ~spectrum, taking into
P
7777777~~~~
~4 N' N~"

.L 1159-66
ACCESSION NR: AT5023145 I
account the 1/v contribution. It is claimed that the method Is simpler than the
three indicator method, and that-it can be employed in biological shielding studies[
Characteristics of the indicators used are given in tabular form. Experimental
results show that, for indicators made of cobalt, aluminum, tungsten, indium,
and gold, the contributions of secondary resonances to total activity are small.
For all other indicators, the contributions are considerable and must be taken
into account in calculations. Determinations of the form of a unknown spectrum
from measurements of the activity of resonance indicators is carried out by the
method of successive approximations. Experiments were also made on applying
the method of resonance indicators to determine the neutron spectrum in stronglyl
absorbing media. Values obtained for the neutron flux are stated to be in good
agreement with calculate &values. The described method for determination of the
form of the spectrum of epithermal neutrons is -claimed to be applicable over the
energy interval from 0. 46 electron volts to 6 thousand electron volts (when the
flux with E=O. 46 electron volts In the spectrum being investigated is 30-40 times
less than in the I/E spectrum) and in the interval from 1. 46 electron volts to 6
thousand electron volts (when the flux with E ='I. 46 electron volts and the I/E
Cori 2/3
-7r -r--.
7 K77 =7 7-

'L. n59-66
ACCESSION NR: AT5023145
.spectra dif y 103-104 times).,.,, ".The authors express their thanks to
A. I.-Y rimerits.
gsil_y I and G. G. Moiseyev for help in carrying out the expe
t
Orig. art. has: 11 formulas, Ifigure and 3 tables
ASSOCIATION: None
SUBMITTED: 00 ENCL: 00 SUB CODE: NP
AEF SOV: 005 ji~;R: 005
Card 3/3

!
ms
s

IBM
IF
L 2L7932-66 EPF(n)-2/EWT(m)/ETC(f)/W(m)
ACC NR, AP5026441 SOURCE CODE: UR/0089/65/019/004/0354/0359
,AUTHOR: -Vasilty8vt G. A.; V?selkinA6 Po_o Yegorov. A..,
11"oiseyev, -=*7anXrar
!Lf~_67 --V-.
ORG: None
TITLE: Attenuation of pile radiation in serpentinite sand
SOURCE: Atomaya onergiyaq Y& 199 no. 40 1965, 364-359
TOPIC TAGS:. nuclear reactor material, nuclear reactor shield
ABSTRACT: The use of serpentine rook for biological oh
Is dia-
cussed. This mineral is found widely dist ted in the Urals Caucasu4
Siberia and Kazakhatant usually assoolated with asbestos deposits such
as the Bazhenov quarries where pure serpeitlidte monoliths of about I cu in
were excavated. Its bound water is liberated only at,temperatures ex-
ceeding 450* C. Thus it can be used as a heat-resisting material for
biological shielding. The concentration of hydrogen nuclei in S03~pen-
tite being about lob% by weightp is quite sufficient for insuring the
attenuation of fluxes oompose'd of interme0'ate and fast neutrons. The
density"of monolithic serpentiat& is about 2.6 ton/ou m while the thermal
conductivity varies betme6n 2.16 and 2,56 kcal/m.hr* C* This material
oould-be easily iaut.'.-,'- The compression strength of blocks made of flerpan-
1/3 ..UW: 621,,0399538.4

ACC_ N21- AP5026"l
tiniter reaches 600 kg/sq am. The shielding properties or serpentinito
fine sand (from Bizhenov deposits) were tested in a water-cooled and
water-moderated research reactor, The.boxes filled with sand were
placed close to the core vessel. The maximum thickness was about 180 am
The sand density was 1.62 ton/cu m. The chemical composition given in a
table shows t -hat-the serpentite sand includes 38.83% of SLO2 and 37.39%
of'11gO. The investigations were carried out assumming "semi-Infinitall
and "energy barrier" geometry, The method of induced activity was used
for determining.the neutron flux attenuation, while the gRmma dose rate
was measured by means of a scintillation dosimeter, The macroscopic
cross-section for fast neutrons In.sand was calculated as 0,0602 cm-1
of which 45% was due to oxygen and 21%-to hydrogen, The variations of
cross sections in serpentite and its main components for different ,
levels of.fast neutron energy was shown in a graph, The peaks and dips
in curves reflected the dependence of cross-saotione upon the presence
of oxygen, The attenuation of fast neutrons calculated on the basis of
threshold-measufgi~ints is'also graphloally illustrated, From these
graphs and a table, it follows that the relaxation of neutron in serpen-
tite sand is the same_as In boron carbide* The protective properties of
serpentite monolith1o-al blocks are considerably higher than those of
iron ore coji6entrates and-only slightly better than thous-of earpentin-
ous concrete4 The spectra of,.fast neutrons were also determined and the
2/3
'P T.

L 2~032-;66
ACC NRI AP5026441-
energy distributions at 00 30t 609 100 and 140-cm, thickness were plotted
for'*varioud,values of neutron flux. The greatest ohanges,.were observed
for energy levels from 3 to 8'Mevo The relaxation lengW;ri~iles from
14.9 to 17 am, The flux attenuation for thermaL.and epithermal neutrons
was also investigated. A certain aooumulation of neutrons was observad
at small'serpentite thicknesses. The relaxation was about 15,2 cm~p
This lougth in amaller.than that (about 20.om) obtained for iron ore
concentrates, The attenuation of does rates of fast and Intermediate
neutrons was the same for tested layer-thicknesses* The dose relaxation
was 15.2 am. The gamma dose attenuation was 22 am for a serpentits
layer of 270 g1sq cm, The experiments showed that the serpentite sand
is as good as the boron carbide, In conclusions it was stated that the
serpentite is not as good as the iron oft concentrates although the
-monolithic serpentite has a lower relaxation length. The serpentite
shieldi-ng properties could be improved by using a mixture consisting of
25% of serpentitb and 95% of iron, 'The full neutron dose relaxation
will be aboutg cm. ORIG* art, has: 4 tablesAnd 5 graphs.
BM COD3 I - '18 SM DATS: 29,Tan65 MG - RZY-0 11. OM RU: 5
Card,

L o5o43-67 Erur (M /DTPW/EW(t)/STI ~q_-AD:LJVG I
j~t-
ACC N& AT6027927 SOURCE CODE: UR/0000/66/ooo/ooo/0120/0122
AUTHOR: Yegorov, Yu. A.; Orlov, Yu. V.; Pankratlyev, Yu. V.
ORG: None
TITLE: Titanium removal cross section for a layer in a bydrogen-containing medium
1-7
SOURCE: Voprosy fiziki zashchity reaktorov (Problems in physics of reactor shielding)
sbornik statey, no. 2. Moscow, Atomizdat, 1966, 120-122
TOPIC TAGS: particle cross section, titanium, neutron cross section, research reactor
ABSTRACT: Removal cross sections for titanium were measured in a water-vater reactor)
of the swimming pool type. Sheets of titanium measuring 70x7O cm were placed near
reactor core with dimensions of 50x43x32 cm. The removal cross section was determined
from the expression
N(r)o(r).N(r-d)G(r- e ~ Zolfo
where N'(r) is the neutron flux at distance r; NI(r-d) is the neutron flux at the di
tance (z-d).when there is no plate; EB is the macroscopic removal cross section; d i:
the thielmess of the plate and G(r) is the experimentally determined correction factor

ACC NRs AT6027927- -2- 1
for geometric attenuation. The results show a removal cross section of 1.7210.06
barns. The removal cross sections determined for detectors with various effective
energy thresholds from 1.1 to 7 Mev coincide within the limits of experimental error.
The minimum distance from the plate used for the removal cross section depends on the
effective thresh ld f th detector. For neutrons with an effective energy of 1.5 Mev
in polyethylene F,;hi: dMance is close to 15 cm. The distance deCri!ased with -u--a-Tn--
WiDeshold. Orig. art. has: 3 tables, 4 formulas.
SUB CODE:t)18/ SUBM*DATE: 12Jan66/ ORIG REF: 006/ OTH REF: 001
Card 212 efe'

L 05o65-67 EWT(m)/EWP(t)/ErI IJP(c) JD/JR/(,D/JH
1,ACC NRs AT6027937 SOURCE CODE: UR/00oo/66/ooo/ooo/0198/0201
iAUTHOR: Yegorov, Yu. A.; Panov, Ye. A.
11 -
ORG: lione
: Experiments with plane slits of various configuration in rad
SOURCE: Voprosy fiziki zashchity reaktorov (Problems in physics of reactor shielding);
sbornik statey, no. 2. Moscow, Atomizdat, 1966, 198-201
TOPIC TAGS: radiation shielding, lead, radiation source, radioisotope, cobalt, gamma
radiation
ABSTRACT: The authors give comparative experimental data for the passage of radiation
through plane slits of various shapes in the shielding of reactors and raliation
sources. The results are compared with respect to the measured distribp.4ion of dose
rate behind shielding with an air slit and a slit filled with aluminum.1/lAn isotropic
C060 source in the form of a platexclasuring 250x250 mm was used in the experiment and
the resultant y-radiation was roc ded by a scintillation gammp-,do5imeter located 40 mm
,from the shielding. The abieldinntudied was made up of lcadf/finitn 90 mm thick with
lateral dimensions of approximately 200 and 450 mm. Additional shielding around the
source and the pickup was used to eliminate the effect of y-radiation scattered frem
surrounding objects. Flat and staggered slits were studied as well as a combination

L 05065-67
I ACC NRt AT6027937
of the two configurations. The experimental results show that the integral increase
in dose rate for the combination slit is equal within 20% to the sum of the relative
dose rate (the ratio of the dose rate behind shielding with a slit to that behind the
solid shield) for the plane and staggered slits. It is also shown that combinations
of two staggered and one plane slit or two staggered slits give an increase in dose
rate equal to the sum of the simple configurations. Orig. art. has: 2 figures, 1
table.
SUB CODE: 18/ SUBM DATE: 12Jan66/ ORIG REF: 001
Z -
4 C

YEGOROV, Yu.D., inzh.; MAGARILLO, B.L., inzh.; POZIN, B.H., inzh.
Concerning the operation of tractors with mounted equipment.
Trakt. i sellkhozmaah. 32 no.10:7-10 0 162. (MIRA 15:9)
1. Chelyabinskiy traktornyy zavod.,
(Traotors)
Ki,

YEGOROV, Yu. G
YEG0RGVj Yu. G. -- "Katerial on the EpizootioloMr of Ito-jeriosis and
Measures to Combat It in 14ningrad Oblast." Min Higher Education
USSR. lAningrad Veterinary Inst. teningradp 1955- (Dissertation
for the Degree of Candidate in Veterinary Sciences).
So.: Knizhnaya Letopisl., No. 2, 1956.

YEJ501"ov, Y11.G.
AKRAMOVSKIY, M.N., kandidat vaterinarn7kh nauk. ra..G., kandidat
veterinarnykh nauk.;BASHKIRTSIVA, Ye.T.., veter1jrv'3'rn;rf takhnik.
Tenting arsenic preparations in monteslauis in lambs. Yeterinarlia
34 no.4.-43-44 Ap 157. WRA lo:4)
1. Beloruaskiy nauchno-iseledo-catellskiy voterinariVy institut.
(Iambs--Diseases and pests) (Tapeworms)
f-A
N

ZHARIKOV, Ivan Semenovich; TE-WIUY,.. riT Grigorlyevich,- BOBKOVA.
Anastasiya Fominichna; DOMASHEVICH) C., red.j YER41W7, V.,
tekhn. red.
(Fascioliasis of farm animals and its control]Fastsiolez sell-
skokhoziaistvennykh zhivotnykh i bor'ba s nim. Minsk, Sellkhoz-
giz BSSR, 1962. 63 p. (15:11)
(White Russia-Liver fluke)
(W'nite Russia-Parasites-Domestic animals)

GOREGLIAD, Kh&S,, akademikj SHIKHAIEYEV, N,F,j MORDASOV, P.M., kand.
vaterinonaukj BITYUKOV., P.Ao. kandoveterinotauki BOBKOVA.. AoF.,
kand,veterin-inau ; YEGOROV Yu Go kand,veterin,natl%
Materialo on anaplasmovis acquired from"'do~inations in cattle
in the Gluak District of the White Russian-&SR. Trudy NIVI
1:72-89 t60o (MIRA 15:10)
lo AN Belorusakoy SSR i-Akademiya sellskokbozyaystvednykb nauk
13e lorusiskoy SSR (~or Goreglyad).
(Glusk Diotriet-Amplaomoois) (Vaccination)

YEGORCV.. Yu.G.,, kand.veterin.nauk
Biology of the lungworm, Nuellerius capillaris. Trudy PIIVI
1:160-170 f60. (MIRA 15:10)
(Lungworms)
OMAN- MINE"
HI,

YEGOROV, Yu*Ge, kand,veterin.nauk; MOROZOVO I.G.0 Yeterinarnyy vrach
------------
Therapy of dictyocaulosis and myelleriosis of sheep using
ditrazine. Trudy HIVI 1:174-178 160, (~MU 35: 10)
(Antheiminties) (Lungworms) (Vote'rinary helminthology)
~T
f

YEGOROV Yu.G. daetarin,nauk; BOBKOVA., A,F.p kandvaterin,nauk
T~~~
2
ThGrapy.of moniaziasis of calves using calcium arsenate. Trud7
NIVI 160, (MIRA 15:10)
'(Calcium arsenate) (Veterinax7 helminthology)

YAGOROT, Tu. L
PAman SM 9i'orgs
P nic silicon, germanium, and tin compounds with
_Tadic&ls..-I.zv. AN SSSR. Otd. khim. nauk no.1:124 J& 157.
(XLRL 10:4)
1. in-otitut,organichookoy khinii im. N.D. Zolinskogo Airadomii sauk
SSSR.
(Organic* miliconi.compouads-Spectra)
(0ormanius organic compouads--Spootra)
(Tin organic compounds-Spoctro)

L 2ogia-,66 zip (e)/DJT (m)/0z1P(t)/F.4P(k) JD
AGG Mt AP6002605 SOURCE CODKI UR/0286/65/000/023/0104/01o4
A-UTHORSs -Poly!~c, D. 0,; tegorov,, Yu. I.; Shereshev, H. A.
OR03 none
TITLEs A device for the automatic control of an electromagnetic owder clutch of
an automobile, Claas 63, No- 142311
SOURCEt Byulleten' izobreteniy i tovarnykh znakov, no. 23, 1965P 104
TOPIC TAGSz electromagnetic device2 clutchs automatic control equipment
ABSTRACT: Thi.9 Author Certificate presents a device for the automatic control of
an automobile electromagnetic powder clutch. The device, including a relay and a
resistor, simplifies the mechanism construction* The rolay has throo windings,
One of the relay-windings is connected to the generator armatures the second to
the shunt winding of the generator, and the third to the winding of tho armature
which automatically disengages the supplementary resistance of the winding circuit
of the clutch when the motor reaches a specified rpm.
SUB CODEI 7.31 SUBM DAM 05M&M
C
ard
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.,~,.)JOgy of '7
Y n,-, t a 11 c
1 30 35.5: 1500
Miarxidullin; Tech. d . Yu. S. Bellchikova.
i d a i nf- rmt lo.,Ljo of of ::,trc
1 44 V .6
a! f-pplications of rara
z C-,J-nical Pictlara and
-al ;.b alao Given, 7hare ar~ 3--.
-"a of~
C11 ..,I or"ZV.10~
DiSPL"_.;r_Cl, ot:h~_, ~.atals Used in lnduz_.-ry
-,Ir Compound-s.
denum. 0. Ya. Jlo-ilevs,'~-ya
_0 b -'ZV
r, C n X. Mlez- .-,;seva
c. al
Zirco.-Ium. 0. Xa. Vog-J.1evskaya
-L. V, Roshchin
Yu. Yegrorov-
3;z~) ou.^ d, s Voroblyo%_

SOV/137-58-7-16217
Translation from: Referativnyy zhurnal, Meta llurgiya,' 1958, Nr 7, p 330 (USSR)
AUTHOR: Yegorov, Yu. L.__
TITLE: Data on the Hygienic Character of the Dust of the Rare Metals
Tantalum and Niobium (Materialy k gigiyenicheskoy kharakteri-
stike pyli redkikh metallov - tantala i niobiya)
PERIODICAL: Gigiyena truda i prof. zabolevaniya, 1957, Nr 6, pp 16-22
ABSTRACT: The study of the character and degree of toxic action of Ta and
Nb showed that: 1) The dust of Ta, Nb, and their compounds form-
ing in industry (powder metzillurgy) is highly dispersable, insoluble
(Ta) or almost insoluble (Nb) in liquid mediums with the pH close to
that of biological mediums. 2) Ta entering the gas tro- intestinal
tract is almost completely elirriinAted by the intestines during the
first few days; ~ Its resorption through the intestinal tract is not
observed. 3) The total toxic action of Ta and Nb compounds is
weak, which fact is evidently explained by the very low solubility
of Ta. 4) The action of the dust of the materials studied on the
pulmonary tissue (on respiratory entry and intra-tracheal intro-
duction) differs depending upon the type of the dust. There are
Card I/Z reasons'for'the assumption of the possibility of development of

SOV/137-58-7-16217
Data on the Hygienic Character of the Dust (cont.
the fibrous process in the lungs upon the prolonged inhalation of the dusts of these
compounds. 5) Processes related to the evolution of the dust demand the applica-
tion of dust removing devices.
1. Tantalum--Toxic effects 2. Niobium--Toxic effects 3. Tantalum Ye. L.
--Physiological effects. 4. NIobiuM--PhysiOj6giaaIf6ffe'cts
Card 2/?.

SOV/137-55-8-18ZO9D
Translation from; Referativnyy zhurnal, Metallurgiya, 1958, Nr8, p286 (USSR)
AUTHOR:
TITLE: Data on the Hygienic Character of Industrial Dust of the Rare
Metals Tantalum and Niobium (Materialy po, gigiyenicheskoy
kharakteristike proizvodstvennoy pyli redkikh metallov- - ta6tala
i niobiya)
ABSTRACT: Bibliographic entry on the author's dissertation for the degree
of Candidate of Medical Sciences, presented to the 1-y Mosk.
med. in-t (First Moscow'MLydical Institute), Moscow, 1958
ASSOCIATION: 1-y Musk. med. iTi-t (First Moscow Medical Institute), Moscow
1. Particles (Airbome)--Physiological factors
2. Tantalum-Physiological factors
3. Njobjum-Physiologica3. factors
Card 1/1
77777--`-~

MORO, YU. Lot
Review of certain dissertations in the field of industrial hyGiene
published in the period 19496-1957. Gig. i san. 23 no.l2t49-53 D 158.
(KIRA 12:1)
1. Iz kafedr7 gigIyagy truda I MoskovRkogo ordena Lenina meditsinskogo
inatituta. imeni IsHe Sechenovas
(INDUSTRIAL HYGIMIN
in Rusnia, review (Han))

4~,_YEGOROVq Yu
Materials on the toxicology of tantalum. Trudy I-go X141
5s19-27 159. 1 (MW 13:8)
1. Iz kafedry gigiyeny truda (zav. - prof* Z.J. Izraellson)
I-go Moskovskogo ordena Lenina meditsinskogo instituta
im. I.M. Sechenova,
(TAIITALUM-TOXICOLOGY)

KASPAROVs A.A.j YEGOROVv Yu.L.
Data on the hygienic aosed=ent of the production of synthetic
fatty acids. Gig.i oan. 25 no.7t3&-42 Jl 160, (KrRA 1415)
lo lz Moskovskogo nauchno-issledovatellskogo instituta canitarii
i gigiyeny Imeni F.? Briomana Mininteretvaziravookhranoniya RSFSR.
(FATTY ACIDS) (CHEMICAL BDUSTRIES-HYGIENIC ASPECTS)

DROGICILINA, E.A.; RASIIEVSKAY4 A.M.1 YE;VGENOVAp M.V.; ZORINA, L.A.j KOZ-
LOVI L.A.j KUZNETSOVA, R.A.j LaZHKOVA, M.N.; SENKEVICII, N.A.; SO-
LOVIYEVA, L.Mdeceased]; SI=AWV, U.N.; IETAVET, A.A., prof., red.;
YEGO-ROV. red.; BULIDYAM,, H.A.s tekbn. red.
[Hanual on periodic medical examinations for industrial workoral Po-
ooble po periodichookim zeditainakim omotram rabochi" prowyahlen-
nykh predpriiatii. By E.A.Drogichina i dr. Moskva, Nledgiz., 1961.
28? P. (MIRA 14:12)
,(inusmm myPIMIE)
6

YEGOROV', Yu.4; KASPAROV,A.A.
Sme problems of hygiene arising in the production of synthetic
fatty acids and higher aliphatic alcohols..Uch.zap. Hosk. nauch.
issl. san. i gig. no.9:34-39161 (MIRA 16:11)
-'Ai
Jis_

YEGOROV, Yu.L.; KASPAROV, A.A.; ZAKHAROT, V.M.
1- - -
Materials ccneerning the toxicology of synthetic fatty acids.
Uch. zap. Mosk. nauch,-isol. inst.san. i gig. no WO-46 161
iMrRA 16:11)
f-

YEGO -Mi.L.1 KASPAROV, A.A.; FUSHKINA, N.N. (Moskva)
Bine disorders in mstab~llc and functional processes of the liver
among vorkers in the production of synthetic fatty acideo Gig*
trtida A prof.2ab. nnonI19-22 'Al. (HIRA 14111)
1. Moskovskiy nauebno-issladovatellskiy institut gigiyerW imeni
F.F. Erismansi. -
(LIVM-DISEASES) (ACIDS, FATTY-TOXICMGY)

YEGOROVO Yu.t., kand.mod.nauk
Problems in labor hygiene at the First A21-J4.Bsian Congress of
Hygionints and Sanitary Phynioians, Gig.i san, 26 no,3:103-106
Vir 161. (MIPA 1417)
1. Iz Moskovskogo nauchnp-isuledovatol'skogo inatituta gigly4ny
imoni. F.F.Erismana.
(INDUSTRIAL HYGIENE)

KLIMOVA) T.Kh.; LORANSKIY, D.N,j YAIIKOVSKAYA) Z.V.; YANIN) L.V.p red.j
YEGOROVi Yu.L., red.; 141RONOVA~ A.M.,, tekhn. red.
(Collection of the most inportant official data or, proble=. of
inclustrial IV,,gicne and industrial sanitation]8bornik vazbnei-
shikh ofitsialtny" materialov po voprosam gigieny truda i pro-
izvodstvonnoi sanitarii. Moskva, Yedgiz. No.l. 1962. 314 P.
(MIRA 15:10)
(INDUSIRIAL 11YGIBITE-1AW AND LIEGI SLAT ION)

ACC NRi AT16007147 SOURCH CODE: UR/3148/60/000/OC
AUTHOR: Lipskaya, N.V.; Deniskin, N.A.: Yogorove Yu.M.; Sbelltirla, V.P.
ORG: None
TITLH: A stationary microvariational station with photomultiplication
SOURCE: AN SSSR. Mezhduvedomstvennyy geofizicheskiy komitet, III razdel programmy
MGG: Geomagnetizm I zemnyye toki. Sbornik statey, no. 4, 1960, 42-47
TOPIC TAGS: geomagnetic Instrumentation, magnetometer, recording precision magneto-
meter 6eomog cA.)&r1e_ MPI)Sc.,,ee lns~~r
ABSTRACT: Mis paper is a description of a sensitive precision magnetographic statio
for'continuous recording of three geomagnetic variation components. The magnetometers
hdve a resolving power of a few tho 9 sandth gamma, at frequencies to Ic/sec. The sensa
is a low inertia-' (under .001 gm.cm ) quartz torsion balance, with a moving magnet at
tached to a light mi,rror. oscillations of a reflected light beam are converted*.into,
photocurrent, intesified by a photomultiplier and amplified to drive a recorder.outpu
is on paper, with 1mm equivalent to .005 gamma. Constant field compensation is provi-
ded by magnets and Helmholz coils. Special coils supply noise suppression feedback ani
stabilize the sensitivity. Automatic range switching and a central,control and sensi-
tivity monitoring unit are provided. Orig. art. has 4 figures
SUD.CODB: 08/ SUBM DATE: None/ ORIG-REN 003
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A005/AO01
Translation from: Referativnyy zhurnal, Geofizika, 1961, No. 2, P. 3,1 # 2G 16
AUTHORS- Deniskin, N. A., Demg ~vYu~.M., Lipskaya, N. V., Osin8kaya, S. V.,
Kheresko, 0. V., Shallting, V. P.
TITLE: A Magnetic Station With a Quartz Microvarlometer
PERIODICAL: V sb.: "Vozmushcheniya elektromagnitn. polya Zemll". Moscow, AN SSS4
1960, pp. 57-62 (English summary)
TEXT: It is reported on 'the development and designing of a magnetic micro-
variation station on the basis of the low-inertial quartz varibmeter which was
proposed by V. F. Shellting (see abstr. No. 2G15). The station is Intended for
continuous recording of-the variations of all three'components of the Earth's mag
netic field with amplitudes of the order of 10-7oe and more, and duration of from V
I see. to many minutes. The equipment consists of three main assemblies: 1) the
microvariometers of X, Y, Z; 2) the photographic recorder with 200 mm in paper
width and 90 mm/hr in speed, which has also a device marking the time; 3) an
automatic band switch relay operated by two photoresistances and permitting the
rays to return in jump onto the phototape after reflection from the microvaricineter
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mirror in case of its depArture from the tape under the effect of an intense
variation of the field. If operating with the automatic banswitch relay, large
angular deflections of the moving system of the responsive element are excluded,
whioh is important for the stabilization of the graduation value. As a result
of the tests of the station, which were conducted in autumn 1957, it burned out
that: 1) the moment of inertia of the moving system Is equal to 10_.'~ g CM2
2) the natural periods of the oscillations of the different variometers lie
within the limits of TOA&I - 2 see at a graduation value of the order of
E ';~ 0.05V/arc minute; 3) the magnetic moments of the moving magnets amount
to about m - 0.5-1 electromagnetic unitn; 4) the shape of the frequency charac-
teristic of the device testifies that the graduation value is constant for all
periods longer than two or three seconds and does not depend on the period of the
perturbing force; 5) the amplitude characteristic is linear within the limits
of the scale width. There are 7 references.
U. Pastovskly
Translation from: This is the full translation of the original Russian abstract.
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40226
S/169/62/000/007/076/149
D228/fD307
AUTHORS: Lipskaya, N. V.9 Deniskinp N, A, and_jpjoroy_t._Yu. 14.*
TITLE: Constructing electromagnetic sounding curves from the
data of observing microvariations in the earih1s na-
tural electromagnetic field
PERIODICAL: Referativnyy zhurnaly Geofizika, no. 7, 1962, 33-34,
abstract 7A218 (V sb. Vopr. teorii i praktiki elektro-
metrii, M., AN SSSR,,1961, 41-55)
TEXT: The study of variations in the earth's natural electromag-
netic field and the determination of the quantitative.correlations
between its magnetic and electric componentEr underlie the magneto-
telluric method. This provides the possibility of establishing the
relationship between the field's recorded values and the geologic
structure of ground at the point of observation. It is noted that
the magnetotelluric method differs from other eloctric prospect-
ing methods in the absence of an artificial fieldoource, in the
depth of propagation of the natural field variations, and in
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constructing electromagnetic sounding... D228/D307
the simultaneous recording of electric and magnetic variations on
the requisite frequency band. This enables the whole frequency
sounding curve to be constructed fron, observ6Ltions made at one
point. The depth of propagation of the natural field variations
grows as the period of the variations increases;, therefore, the
frequency band of the recorded variations determines the eq -uip-
ment's field of application. There are induction-type installation,;
and equipment, based on the magiietootatic principle. The field
uartz microvariation station of the Institut fiziki Zemli AN SSSR
nstitute of Physics of the Earth, AS USSR) is described. The sta-
N
tion is suitable for continuously recording the three magnetic
field components lix, Ify, and.11Zin the frequency range from I to
several thousand parts of a hertz. It consists of a receiving par'
(microvariometer, clarifier, photomultiplier); and control, re-
cording, and poiver-supply..panels, placed 30-m from the receiving
part. Tests ol*' the apparatus confirmed that there is a linear re-
lationship between the amplitude of the changes in the magnetic
field acting on the microvariometer and the values of the recorded
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S/16 62/000/007/076/149'
Conctructing electromagnetic sounding ...D228YD307
photocurrent. The current recording curve is reproduced on a cer-
tain acalo. without greAly diatorting the curve for the miorovaria-
tions of the moctoured field oompononto with a variational range of
up to 2 - 3 e and with periods, varying from 3 sec to several mi-
nuten. The ratio of the ranges of variationat recorded by two in-
stallations, remains constant with a precision of up to 4 -~ 8cf.. The
amplitude and phase characteristics of the field equipment are ci-
ted, as are vector diagrams, ch4racterizing the instantaneous po-
sitions and the magnitude of the horizontal components of the magne-
tic and electric field vectors for the variations with periods of
T equalling 32 and 210 sec. The authors consider examples of the
recording of electromagnetic field variations at two points of the
Diieprovsko-Donetskaya Depression with known geol6gic sections. Mhen V~
constructing the frequency sounding curves ratios were calculated
for the amplitudes of the variations of two mutually perpendicular
components of the electric and magnetic fields; these were recorded
at the same moment of time and have an identical period. The impe-
dance was determined from the formulas:
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Conutructing electromagnetic sounding ... D228/D307
2
and
PK fly PK ;:,5 HX
The experimental curves of PK were compared with the theoretical
curves of self-potential field electroaounding for a three-layer
medium; these latter curves were calculated forJU = P21PI = 16 and
32, v = h2/h, = 1.0 and 1.5, P3 = co , h3=oo. The comparison gave
satisfactory results. It is noted that despite the equipment's abi-
lity to record microvariiitions with periods of down to 1 see, no
variation with a,p6riod of below 10 see was recordedAn the opera-
tiona. The value T = 10 see appears to be the boundary of a cer-
,tain unique "aboorption'band"t whose authenticity of existence can
-.only be confirmed by subsequent observations* Z-Abstracter's notet
AomglM trazielations-t
I aT,

LIPSKAYA, N.V.; IjZlTISjK'IN, N.A.; YEGOOVp Yu.11.
ile:xltr; of j1ectromaLnotic vounding in the central area of the
jIA-I,-,,r-Donots Dapreu3ion. Izv. All SSR. Sor. goofiz. no. 3:407-
-IIRI, 14:2)
1. !-1,- L,...; vt 'L,ziki Zemli All SSSR.
m-rovla Re,rdon (Chernigov Province)-Electromagnetic prospecting)