THE SOVIET JOURNAL OF ATOMIC ENERGY NO. 3

• Document Type: CREST
• Collection: General CIA Records
• Document Number (FOIA) /ESDN (CREST): CIA-RDP10-02196R000100090004-1
• Release Decision: RIFPUB
• Original Classification: K
• Document Page Count: 16
• Document Creation Date: December 23, 2016
• Document Release Date: April 3, 2013
• Sequence Number: 4
• Content Type: REPORT

Declassified and Approved For Release 2013/04/03: CIA-RDP10-02196R000100090004-1
ATOMITalt
HeprHM
Number 3, 1956
ATOMIC SAFETY MEASURES
The Soviet Journal of
ATOMIC
ENERGY
IN ENGLISH TRANSLATION
CONSULTANTS BUREAU INC.
227 WEST 17TH STREET. NEW YORK 11, N. Y.
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NEWS OF FOREIGN SCIENCE AND TECHNOLOGY
CONSTRUCTION OF 'RESEARCH REACTORS IN ENGLAND
The atomic energy administration of the United Kingdom is building at Harwell two reactors, "Dido" and
"Pluto", intended for broad investigations in physics' and technology. Furthermore it is planned to construct a
reactor of the "Pluto" type in Douneray. In 'addition, England is providing aid to Australia in the building of a
"Dido" type reactor.
Fig. 1. Construction of new reactors for physical investigations at Harwell.
A) Reactor "Didb", designed for general physical investigatiOns; B) construction of a reactor
of the "basin" type, of .100 kw power and with neutron flux. 101s neutrons per cm2/sec; C)'
reactor "Pluto', similar to the reactor "Didb", but designed for testing fuel elements.
. -
. Tank for heavy wa Graphite
te4 tp
200 cm in diameter flectof
I .
VC\-1
16 Level of h av /0
90 .1
:50
30
0
10
10
'V.
110
130
140
7.10"
8,10"
17,10q
?
..... . T.T.7?,5P,3?S.9P19.5P.7,2?,T,VisPcm ?
?? ?
Fig. 2. Undisturbed distribution of thermal neuttons? in the
reactor "Dido" (all values in neutrons per cm2/..sec).).
'
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Fig. 3. 1) Aluminum tank for heavy water; 2).1evel of heaVy'water; 3) fuel element; 4) vertical experimental
channel; 5) guides of six emergency rods 6) experimental channel 10.16 x 5:08 cm; 7) biological shield;
8) graphite reflector; 9) experimental channels 30.48 x 20:32 CM; 10) lead heat shield (water cobled); 11) steel
reactor vessel with boron covering; 12) experimental channel for takirigneutrons:froni the active zone; 13) ex-
perimental channel for taking neutrons from the graphite reflecter;:14)',vertical channel from the graphite
zone; 15) concrete shield; 16) supports of reactor; 1.7),first'flOor; 18) thermal column 19) bracing of reactor
foundation; 20) steel upper 'lid Of thickness 25,4 cm 21) experimental channel.
The "Dido" reactor is intended for use in physical experiments for example the measurement of neutron
cross sections, and the study, of the parameters of various types of reactor lattices;- besides this, the irradiation of
small specimens of materials can be carried out in the reactor. The moderator and heat transfer agent of the
reactor is heavy water,. and the fuel is enriched uranium (about 6 kg,. of which 2.5 kg is Um).
The active zone of the reactor, with a volume of about 0.3 m3, has the form of a cylinder of height 60
cm and diameter 86 cm. It is composed of lamellar fuel elements whose .filler is a mixture of uranium with
"-
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aluminum. The active zone is located in the center of an aluminum tank of height 2 m and diameter 2 m. The
reflector of the reactor is of graphite, 60 cm thick. The reactor and reflector are inclosed in a steel jacket fil-
led with helium.
The nominal power of the reactor is 10 megawatts, with neutron flux 10" neutrons per cm2/sec. The maxi-
mum possible flux is 5.10" neutrons per cm2/sec. The starting of the reactor is set for autumn, 1956.
At the end of 1957 the two reactors of the "Pluto" type are to go into operation. The construc,tion and
physical characteristics of these reactors are similar to those of the reactor "Dido", but their purpose is somewhat
different; they are designed for the long-time testing of fuel elements. For this purpose it is planned to install six
or eight testing loops in the reactor "Pluto".
I. S.
LITERATURE CITED
[1] The Journal of the British Nuclear Energy conference 1, 1, 3 and 35 (1956).
[2] Engineering 180, 4673, 235 (1955).
A REACTOR WITH AN ORGANIC MODERATOR
According to reports there will be set in operation at the end of this year a reactor with an organic modera-
tor (OMRE) with power 5 to 15 megawatts. The moderator used in the reactor is diphenyl, and the fuel is highly
enriched uranium.
Preliminary experiments have shown the good stability of the organic moderator in the neutron field and
insignificant deposition of precipitates (which had been feared earlier) in the form of a film on the surface of
the fuel elements.
The reactor will probably be built by the Atomic Energy Commission, together with the "North American
Aviatien" Company'in Arco, Idaho, U.S.A.
I. S.
LITERATURE CITED
[1] Nucleonics 14, 1, 14 (1956).
[2] Atomic Energy News Letter 15, 2(1956).
ECONOMIC INDICES OF ATOMIC STATIONS
Quite recently there have appeared in the American literature communications on the economic indices
of certain reactors.
Admiral Rickover announced that upon the third loading of an active zone? of the reactor PWR at the Ship-
pinEport atomic station the cost of electrical energy will be lowered from 5.2 to 1.5 cents/kw -hr.
? In the reactor PWR it is planned to load successively the assemblies of different active zones.
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At the first loading of an active zone the cost of energy is composed of fixed expenditures (1.5 cents/kw-hr.)
the cost of preparing fuel elements, the cost of zirconium and other construction materials (3.9 cents/kw-hr.) and
operating costs (0.3 cent/ kw-br).From these 5.7 cents/ kw-hrls subtracted- the value of the processed fuel, equal
to 0.5 cent per kw-hr.
At the second loading of an active zone the total cost of the energy will be reduced to 3.2 cents per kwl-hr
through the lower cost of fuel, a decrease of operating cost, and the increase of the power from 60 to 90 mega-
watts. At the third loading of an active zone the cost .will be lowered to 1.5 cents/kw-hr. For the loading of the
first active zone the working time of the reactor will be equivalent to 8000 hours of operation at full power,
which means, including idle time of the reactor, more than one and one-half years. The exact working time
with the first active zone is not known, since at first the reactor will be mainly used for experimental purposes.
Its power will be increased gradually: 1st year;, 10% 2nd year, 20/0; 3rd year, 40%; 4th year, 60%; 5th.year,
either 80170or full power.
The third loading of an active zone in the reactor will be accomplished not ^,arlier than 1965.
The firm "Alco" has released formerly secret data on the cost of electric energy from the portable army-
reactor APPR, which is being constructed in Fort Belvoir (Virginia).
The fuel component of the cost of electrical energy will not exceed 0.95 cent/ kr-hr. This sum include
0.6 cent/kw-hrcostof fuel calculated at 25 dollars per gram of U285, 0.25 cent/kw-hrfor preparation of fuel ele-
ments, and 0.1 cent/kw-hrfor reprocessing. Operating expenses for an installation of power 2000 kw will amount
to approximately 0.15 centOW-hr. Fixed costs will be 0.58 cent1kw.7hr afloaldlactor 80%.
Thus the cost of electrical energy will come to about 1.68 cents/kw-hr. . The cost of energy from an
analogous coal-burning station is 1.4 cents/ kw.-hr..
I. S.
LITERATURE CITED
[I] Nucleonics 14, 1, 14 (1956).
A PERFECTED METHOD OF FILM DOSIMETRY
The Oak Ridge Laboratory has developed a film dosimeter with which the following measurements can
be carried out:
a) determination of dose and radiation energy of x-rays;
b) measurement of dose of y -rays;
C) approximate determination of dose of 8 -rays acting alone;
d) approximate determination of dose of mixed 0 - and y -rays.
For this purpose a system of filters is used to simplify the measurements and make them more exact.
An ideal filter for the measurement of a broad spectrum of x-rays is one with which the degree of blacken-
ing of the film depends only on the dose of radiation and not on the energy of the protons. Three types of filter
are described in the report:
1. The filter consisting of the material of the cassette body, conventionally designed "OW" -1-Cropen
window".
2. The "OW" filter plus 1.56 mm of cellulose acetate, called the "plastic" filter.
3. The filter of "OW" + 0.25 mm tungsten + 0.5 mm cadmium + 0.5 mm cellulose acetate, called the
"shielding" filter.
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a
,
7
7
C,
?
7
"OW" and "plastic"
"shield i
100
200, 300 400
kv (eff)
500 500
700
Fig. 1. Dependence of blackening density of film on
energy of radiation (dose 200 mr). Upper curve with
"OW" and "plastic" filters; lower curve with "shield-
ing" filter.
?
C.)
? e.
V)
24
tga
:28 20
18
:g 16
C. /4
? 12
100 200 300 400 MO 600 Vti
kv (eff).
Fig. 3. Dependence of the ratio of the blackening
densities for "plastic" and "shielding" filters on
the energy of the radiation.
12
10
/28
,a4
02
ii 500 1000 1500 2000 2500 4000
m (rJ e:p.)
Fig. 2. Typical calibration curve for 8 - and y -radia-
tions with the different filters.
1) ylRayt of radium, "plastic" filter; 2) y -rays of radium,
"shielding" filter; 3) 8 -rays of uranium, "OW" filter.
All three filters are placed side by side in one cas-
3
3500
sette so that each of them acts separately.
Fig. 1 shows a comparison of the blackening densi-
ties of the film with the "OW" and "shielding" filters
for a 200 mr dose of radiation at various energies. The
curves show that the blackening densities with the "OW"
and "plastic" filters are equal. But for the action of
8 -particles the blackening under the "OW" filter is
greater than under the "plastic" filter, and on this basis
one can determine the dose of 8 -radiation in cases of
mixed action of 8- and y -rays from the difference of
the degrees of blackening.
The "OW" filter together with the film wrapper
has thickness 80 mg/cm2..I3-rays of penetrating power
7 mg /cmg and over are considered harmful to human
beings.
Figure 2 shows a typical calibrating curve for various
radiations with the different filters. To determine the
dose of 6 -radiation one needs only to multiply the difference, of the readings with the "OW" and "plastic"
filters by 1.5.
The dose of photons is determined in the following way:
1) from the calibration curve one finds the dose for y -rays with the shielding filter;
2) by subtracting the density of blackening for 8 -rays from that for y -rays with the "plastic" filter one
finds a "correction" density, and then the dose corresponds to 1/10 of the "correction" density. The greater
of the two doses found is taken as the dose of x- or y -rays.
Although the determination of the dose of photons by the method described does not depend on the energy
of the radiation, the filters make possible the determination of the energy of the radiation in effective kilovolts.
This may be needed in case a knowledge of the relative "depth" of the dose is required. The determination of
the energy of the radiation is made from the curve shown in Fig. 3, which gives the ratio of the degrees of blacken-
ing under the "OW" or the "plastic' filter to that under the "shielding" filter as a function of the energy of the
photons.
S. L.
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LITERATURE CITED
[1] E. D. Gupton, Radiology 66, 2, 253 (1956).
DOSIMETRY BY MEANS OF GLASS
The majority of existing methods of dosimetry, based on ionization measurements or on the calorimetric
principle, do not provide speed, accuracy, and constancy of readings in the measurement of large doses. The
changes of absorption for the Visible spectrum of most sorts of glass when irradiated with doses of the order of
106-107 r.e.p. make it possible to use glass for the measurement of large doses of .adiation. As a dosimeter
glass has a number of advantages that make its use in this field very attractive. These are: chemical inertness,
insolubility, small size, and durability. But there are a number of factors limiting the use of glass. The most
important are low sensitivity, linearity of readings, and the rapid fading of glass at room temperature.
In an investigation of these phenomena it was
found that the addition to glass of elements such as
cobalt and silver considerably increases the sensitivity
of the glass to radiation and reduces the speed of its
fading after irradiation. These types of glass have
5 an absorption band for visible light in the part of the
spectrum near the ultra-violet, and thus the investi-
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activated with silver: 50% Al(P03)3, 25% Ba (P03)2,
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