JPRS ID: 9833 USSR REPORT LIFE SCIENCES BIOMEDICAL AND BEHAVIORAL SCIENCES

• Document Type: CREST
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• Document Number (FOIA) /ESDN (CREST): CIA-RDP82-00850R000400070014-5
• Release Decision: RIF
• Original Classification: U
• Document Page Count: 16
• Document Creation Date: November 1, 2016
• Sequence Number: 14
• Content Type: REPORTS

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JPRS L/10099
5 November 1981
~ W`orld~vide Re ort
p
NUCLEAR DEVELOPMENT AND PROLIFERATION
- cFOUa 13is,~
Y
- Fg~$ ~OREIGN BROADCAST INFORM~;TION SERVICE
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NOTE
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COPYRIGHT LAWS AND REGULATIONS GOVERNIIdG OWNERSHIP OF
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JPRS L/10099
5 November 1981
WORLDWIUE REPQRT
NUCLEAR DEVELOPMEfVi(' AND PROLI FERATIOfJ
(FOUO 13/81)
- CONTENTS
~ E~!ST EUROPE
CZECHOSLOVAKIA
Health H~zards at Nuclear Power Plant V-1 A~asessed
(Jozef Carach, et. al.; BRATISLAVSIUs LEKARSKE LISTY,
Aug 81) 1
su$-sAxaxAx aFRZCA
NIGER
Authorizations for Uranium Exports ~uring Firat Half 1981
(MARCHES TROPICAUX ET MEDI~~RRANEENS, 4 Sep 81) 11
Briefs ~
Uranium Sales Policy 13
Japanese Uranium Exploration Agreement 13
- a - [ I II - 'WW - 141 FOUO ]
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CZECHOSLOVAKIA
HEALTH HAZARDS AT NUCLEAR POWER PLANT V-1 ASSESSED
Bratislava BRATISLAVSKE LEKARSKE LISTY in Slovak No 2, Aug 81 pp 231-240
[Article by Jozef Carach, Ma.ria P etrasova, Tomas Trnovec and Dusan Ondris: "Med-
ical Care Aspects of Nuclear Power Engineering in the SSR." R~,gional Hygiene
Center in Bratislava, Director po cent F. Schulz, M.D.; the Center of Physiolog-
~ ical Sciences of the Slovak Academy of Sciences; ~he Institute of Experimental
Pharmacology in Bratislava, Direc tor pocent L. Ben.es, R.N.D., Candidate of Sci-
ences; and the EBO Factory Health Care Center in Jaslovske Bohunice, Head Physi-
_ cian M. Homola, M.D.]
- [Text] As a developed socia~ist country, Czechoslovakis decided to cover further
power demands by building nuclear power planCs. According to the plan's expecta-
tions, nuclear pow~r plants with a total power output of 8,000 MW will be put in
operation before 1990. The firs t Czechoslovak nuclear power plant had an experi-
mantal character; it was operated from 1972 to 1977 and fu~~illed its program.
The second Czechoslovak nuclear power plant, V-1, is of a different type, based
on a different conception with many unique technological elements. Before the
end of the century, only this typ e of nuclear power plant will be built in our
country, and our first experience from the hygiene inspection in this facility
can significantly influence the hygiene approach to further stages in nuclear
power plant construction development.
- General Principles and Provisions for Staff's Health Protectian in the V-1 Power
Plant
Division of Space According to the Extent of Ionizing Radiation Hazard
All technological systems and equipment conta:Lning radioactive media are enclosed
in hermetically sealed and screened spaces, equipped with an independent ventila-
tion system. A so-called monitored zone has been established, where only a cer-
tai.n number of employees is allowed to enter under precisely specified conditions.
- The uionitored zone areas are divided into unattended, semiattended and attended
areas. The unattended areas include hermetically sealed boxes (steam-generator
boxes, the volume compensator box, the radioactive media treatment station boxes,
the~reactor :~haft, the ro~ms with the filtering apparatus for the ventilation
systems, etc.). These spaces are characterized by high levels of external gamma
' radiation and the presence of radioactive substances. Z'he staff enters the
�1
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semiattended areas ~nly with special permission for a certain period of ti.me and
� is monitored by the members of the dosimetric service (tfie reactor fiall, the main
circulation pumps and main closing fittings contro~. rooms, the measurement and
regulation rooms, etc.).
, In the attended areas, the radiation hazard is very low during regular operation
and the staff's movements witbin this zone are not limited by time (the reactor
hall control room, attendance corridors, communication corridors, etc.).
2. Dosimetric Monitoring Systems
With respect to the importan~e of the harmful effects of ionizing radiation in the
working environment, an exten.sive dosimetric system is regularly installed in
_ nuclear power pla~t facilities. 'The system has been designed to measure the radi-
ation characteristics of the working environment and technological media (air,
water).
a) Biologic Dosimetry
Biologic dosimetry concerns the radiation factors in both the working and living
environment, to which the staff and the aearby population are immediately exposed.
On the other hand, technological dosimetry utilizes the monitoring cf radiation
- f.actors for the control of the conditions of technological equipment.
= The stat~onary part of the biologic dosimetr~c system processes information ob-
tained through individual detectors placed in various space~ of the nuclear power
plant monitored zone. The information is signalle~ by sound or lignt whenever
the adjusted le~els have been exceeded in the detector's vicinity and in the
radiation control block manitoring room, where the information is recorded at the
same time. The volume activities of gases and aerosols are measured in the work-
ing site atmosphere, along with the levels of the exposure gatmma-radiation input.
Dosimetric instruments serve for periodical operational control of the situation
in radiation.
b) Technologic Dosimetry
Of the wide spectrum of various measurements, performed to obtain information con-
cerning the present conditions of the reactor's technological equipment and pri-
mary circuit through monitoring the active products, measuring 132I and 134I ac-
tivities continuously is most important; next comes exposure gamma-radiation input
to the prim.ary circuit piping, in active-water treatment stations and the like.
The penetration of radioactivity into the secondary circuit is monitored by mea-
~ suring the exposure input on the live-steam piping and the total beta activity
of the steam-air mixture taken from the turbine nozzles.
Samples of the media from the primary circuit and other technological circuits
are taken to determine the total beta activity in laboratorj.es, the tritj.um ac-
tivity, as well as the activity of individual fissile and corrosive products.
Gamma spectrometry and liquid scintillation spectrometry are used methodically.
Timely discovery of failures in technological equipment through monitoring the
radioactivity of the media is also important from the point of view of radiation
safety.
2
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3. Radioactive Waste Monitoring
- The radioactivity of waste products being let out through the ventilation chimney~
is measured with equipment which permits determining the total beta activity of
rare gases, long-term aerosols and steam~ 131Z. ~e data obtain~e~ are transferred
to the radiation control monitoring room. Tritium in w~stz ~roducts is measured
in samples continuously taken through capturing air humidity on silica gel.
~ 4. Personal Dosimetry
The staff dose exposure to external beta radiation and gam~!a radiation is measured
with the method of film dosimetry, complemented by ~easurements using ionizing
chambers and thermoluminescence method. The dose exposure to fast n~utrons is
measured with a trace dosimeter. Every member of the staff is equipped with a set
of personal dosimeters corresponding to the radiation characteristics of the en-
vironment in which he works.
5. Monitoring the Surface Contamination of the Staff Members
Stationary dosi.metric instruments have been installed at the exit from the moni-
- tored zone for measuring the surface contamination of the staff inembersR clothes
and bodies. Portable dosimetric instruments serve in opErative monitoring of the
suxfaca contamination of staff inembers as well as areas.
6. Monitoring Internal Contaminati.on of the Staff Members
- The Plant Health Center monitors internal containination in the staff inembers.
The staff inembers are examined according to their position and the type of work
they perform. Selected professionals, such as shift dosimetrists, maintenance
staff inembers, operators of the reactor's auxiliary systems, chemists manipulat-
ing with radioa~.tive samples and the like, are examined routinely at 1 month
periods.
Further, the staff inembers participating in wock assignments involving increased
hazard of internal contamination or those having been surface contaminated to a
_ certai.n significant extent are examined regularly. In both cases, the basic
examination consists of ineasuring the radioactivity with an entire-body computer,
determination of the radioactivity of the thyroid gland, checking the internal
contamination by tritium, and determining the total radioactivity from the beta-
spectrometric and gamma-spectrometric examination of biological material.
Preventive medical examinations also include monitaring internal contamination.
In this way, internal contaminatian is examined in every member of the staff sub-
ject to some exposure for at least 1 year. The extent of this examination de-
pends on the frequency and type of work performed in the environment with ioniz-
ing radiatian.
The dose exposure of the V-1 power plant staff inembers due to internal contamina-
tion ranges within very low levels. In several tens of cases, increased tota'1
beta activity, the presence of 134Cs, 137Cs and tritium have been found. Not
even a single case of the occurrence of radioactive iodine has been discovered.
3
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The d~se e~osure from internal contamination has never exceeded the value of
1 mSv.
Up-To-Date Hygiene Experience From the Operation
All physical parts of the nuclear power plant were put into operation according
to a scientific program and instructions prepared in advance. The reactor reached
the critical state on 27 November 1978. The process of activating the reactor for
power generation at various output levels up to the nominal output was completed
on 3J March 1979. Since then, the V-1 power plant has been in trial operation,
during which the provisions for radiation protection iracorporated in the design
are being tested thorough~y, 2ogether with other characteristics.
1. Contamination of Technological Circuits
The radiation hazard in a nu~.lear power plant is related directly to the conditions
of the reactor and its primary circuit, primarily to the inventory of fissile and
_ corrosive products. Ap art from nuclides with short half-life period of disinte-
gration, such as 16N, 42K, 24Na, whose specific radioactivity under the conditions
of the reactor's nomi~al output ranges within the level of 106Bq.kg'1~ 131I~ 134I~
91gr~ 134Ba and 144Ce nuclides were also found in the cool.ing water of the primary
_ circuit, their specific activity levels ranging between 102 - 104 Bq.kg 1. From
corrosive products, the presence of 56~~ 60Co and 187W has been ascertained.
Their radioactivity does not exceed 1.85-1058 .kg 1. The volume activity level of
3H in the primary circuit is maintained at lO~Bq.l-1, which is by one order less
t.han the value pxescribed in the design.
No significant leakage has been found in the technological equipment of the pri-
mary circuit and its auxiliary circuits, which might lead to significant contami-
nation of the working areas of the power plant. No defects in the hermetic seal-
ing of the fuel rod casing have been found, either.
2. External Radiation Hazard in the Power Plant Areas
The gamma-radiation dosP input level in the attended areas (Table 1) keeps at
_ tenths of Gy.h 1, which is almost the level of a natural background. Exception-
ally, increased values have been measured in the fittings attendance room where
the box for the water intake from the primary circuit is situated.
~ In semiattended areas, higher ?evels of gamma radiation have been found, ranging
between the levels of ones to tens Gy.h'1. The inputs in the unattend~ed areas
are related to the types of technoZogical equipment and the ma.gnitude of the
radioactivity p~resent in this equipment. All these areas are closed to staff
members during the rsactor's operation.
3. Surface Contamination and Radioactive Aerosols in the Power Plant Areas
- It follows from the measurements (Table 2) that surface contamination has been
ascertained only exceptionally, namely in the areas of the water-treatment sta-
tion of the primary circuit in the steam-generator and main circulation pumps
4
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measuring rooms and in the area where the radiation of the water from the primary
circuit is monitored. T:~e contamination fiad been caused by leakage through vents
and seals, and having been discovered, it was stopped immediately.
The volume r.adioactivity of aerosols in both attended and unaLLended areas ranges
about the level of ones to tens mBq.l-1. Higher values have been found in the
radiation monitoring room of the primary circuit water and in the roams with steam-
generator and ma.in circulation pumps measuring instruments, as a result of surface
contamination.
The voliune of beta activity of rare radioactive gases ranges between ones and tens
Bg.l-1.
4. Radiation Exposure of Staff Members
The high technological standard of the primary circuit equipment is reflected in
low dose exposure of personnel. Not even for a single month did a collective
dc~se of external gamma radiation exceed 0.02 Sv; nearly 800 workers were examined
_ ~Table 3). No significant differences weie found between the evaluations per-
formed during the gradual process of activating the plant and thos~e pErformed dur-
ing trial operation with the nominal output. Analyzing the distribution of the
collective doses to various groups of professionals we found out that beside the
equipment attendance staff, also chemists, dosimetrists and leading technical
personnel were exposed to doses during the process of physical and energetical
activation of the plant, whereas the attendance and maintenance personnel almost
- exclusively participate in the dose exposure during trial operation.
- 5. Radioactive Wastes
The results of monitoring the radiaactive wastes in the ventilation chimney
(Table 4) testify of a good radiation situation during the operation of the first
block of the V-1 power plant. The radioactivity of rare gases (radioisotopes of
xenon and crypton) amounts to several percent, aerosol beta activity reaches only
several hundredths ~f a percent and 131I only several tenths of a percent of the
permissible limits.
6. Liquid Radioactive Wastes
All waste water leaving the V-1 power plant is monitored dosimetrically. Year
limits have been determined for the discharge of radioactive substances into the
living environment, further specified for fissile and active corrosive products
and tritium. The up-to-date monitor records show that the amount actually dis-
charged reaches the perinissible limits only partially. The average value of the
total beta activity of the waste water discharged from the power plant in the
first half of 1979 is 2.34 Bq.l-1. The share of the content of 90Sr and 137Cs
in the total beta activity is 70 percent. The radioactive substances discharged
into the living environment cause to the population living in the plant's vicin-
ity negligible dose exposure, if compared with the exposure to natural radio-
active background.
5
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Discussion
Compared to other technologies, the pressure-water nuclear reactor technology is
most widely used and evaluated as a whole from various aspects, including radia-
tion exposure, it reaches the best parameters. The V-1 power plant is equipment
ma.nufactured in series. The favorable experience with the radiation situation in
hoth working and living environment of a power plant of this type has been dis-
cussed in literature many times (Golubev ~nd tea~, 1974; Martin, 1977; Murphy and
team, 1977; Vohra, 1978; Voznesenskij, 1978).
Our present experience with the operation of the V-1 has been equally favorable.
An overwhelming majority of nuclear power plants operating throughout the world
at present are essentially of an analogous conception. We know from both our own
and foreign experience that fro~ the point of view of radiology, it is necessary
to keep in mind two important factors.
1. The so-called human factor is accentuated as always more important. Despite
advanced technological and engineering safety of the facility, mistakes in judg-
ment, inadequate observation of operational regulations and duties can lead to
_ serious failure with subsequent leakage of a significant amount of radioactive
_ substances into the environment. Therefore, high professional standards, sys-
tematic supplementary training and testing the operational staff is emphasized.
Technical tests aim at testing the knowledge of the physics of the reactor, tech-
nology and nuclear and radiation safety.
During operation some parts of the technological equipment wear out gradually,
leakage occurs as a result of the.damage of the compactness of the structural ele-
ments due to corrosion and the like. The ever-gr.owing demands for maintenance
and repair of the radioactive equipment result in the increase of individual ex-
posures as well as the increase of the leakage of radioactive substances into the
living environment.
At present, the need to obtain electric power, on the one hand, and the biologic
' ~ zard resulting from this activity, on the other hand, are often discussed and
- considered. In our country, this question has been discussed in detail by
Paulicka and Trnovec (1976); they pointed out that even in the case of optimal
coverage of all of the Czechoslovak area with nuclear power pZants, no inadequate
biologic hazards threaten as a result of leakage from these facilities which might
be reflected in the increase of lethal diseases or perhaps undesirable genetic
consequences.
S ummary
Factors of radiation hygiene in the operation of a nuclear power plant of a pros-
pective type with a water-pressure reactor are surveyed. Both home and foreign
- experience shows that generating el.ectric power using ti~s type of nuclear tech-
nology is compatible with Iow biological hazard.
COPYRIGHT: VEDA, Vydavatelstvo Slovenskej Literatury, Bratislava, 1981
9814
CSO: 5100/3001
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NIGER
AUTEiORIZATIONS FOR URANIUM EXPORTS DURING FIRST HALF 1981
Paris MARCHES TROPICAUX ET MEDITERRANNEENS in French No. 1869 4 Sep 81 p 2278
[TextJ According to uranium export authorizations issued by decree published in
the Official Gazette of the Niger Republic, the Niger government authorized exports
_ of 4,846.9 tons of uranium during the first half of the year, to be delivered during
1981 to six countries: France, Libya, Japan, Spain, Federal Republic of Germany and
Iraq.
France will be Niger's major customer, with authorized imports (decreed on 3 and 7
riarch) of 2,293.3 tons, as compared with 1,344.3 tons in 1980 and 100 tons i.n 1979.
It is followed by Libya (1,212 tons in 1981, against only 380 tons in 1980), Japan
- (816 tons), Spain (300 tons), Federal Republic of Germany (with ~25 tons of uranium
for 1981, in comparison with 250 tona in 1980) and finally, for the first time,
Iraq with 100 tons.
Out of these six customers, four, through subsidiaries, are shareholders in the
capital of the two IViger uranium mining firms, SOMAIR (Air Mining Comuany) and
COMINAK (Akouta Mining Company). Thus they have uranium export rights allocated
on the basis of their share in the capital of the mining companies.
Niger, for its part, holds 33 percent of SOMAIR's capital and 31 percent of COMIVAK's
capital, thr~ugh ONAREM (National Mineral Resosrces Board).
In SOMAIR, Niger's partners are France (General Nuclear Materials Company with 26.96
~ percent, French Uranium Company with 11.79 percent, M~.natome with 7.58 percent and
P-tokta Mining Company with 7.58 percent), FRG (Urangesellschaft with 6.58 percent)
and Italy (Agip Nucleare with 6.53 percent).
In COMINAK, ONAREM is joined by France (COGEMA with 34 percent), Japan (Overseas
Uranium Resources Development with 25 percent) and Spain (Empresa Nacional de Uranio
with 10 percent).
- Consequently only two countries, Libya and Iraq, which have no shares in the capital
stock of the two Nigerien uranium companies, were importers of Nigerien uranium in
1981, purchasing it from ONAREM.
In examining the data in the Official Gazette of the Republic of Niger, it is found
that although it is the first time that Iraq has bought uranium from Niger (decree
of 28 January 1981), 1979 (150 tons) and 1980 (180 tons, then 200 tons). Economic
observers note, however, that it fs the first time that this country, which has no
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processing plant, has purchased such a large amount of uranium (1,212 tons). (For
possible uses of this uranium by Libya, see under "Libya".)
French imports (2,293.3 tons) also register a clear increase over 1979 (100 tons)
and 1980 (1,344.3 tons). Out of these 2,293 tons, 600 will go to the Atomic
Energy Commission, as a special purchase outside the quota.
Japanese and Spanish imports have remained at about the same level as in previous
years, while the FRG has reduced its demand by half from 1980 (250 tons) to 1981
(125 tons).
According to the Official Gazette, exports authorized during the first 6 months of
the year will `be made "in the course of 1981." It is rather unlikely, observers
ncte, that further export authorizations will be issued for this year, since the
total tonnage already authorized during the first half of 1981 exceeds the domestic
production capactty by about 500 tons.
- CaPYRIGHT: Rene Moreux et Cie Paris 1981.
9805
CSO: 5100/4965
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NIGER
BRIEFS
URANIUM SALES POLICY--By publishing in the JOURNAL OFFICIFL of 27 August a list of
all sales of uranium decided on during the first 6 months ~f 1981, the authorities
confirmed their resolution to make commonplace trade in a highly strategic product.
Deliveries to Libya increased six times (1,212 tons as compared with 200 in 1980)
and an initial purchase by Iraq (100 tons) was recorded, Whereas these two countries
hav~e been blacklistec~ in particular by the United States which, invoking nonprolif-
eration, would like to prohibit the th ird world states from access to nuclear en~rgy,
even to the atom bomb. The position of President Seyni Kountche is clear: "We are
selling to any customer who, while accepting our pri~cea, satisfies the purchase
conditions set by the international com~i~sion in Vienna." The loading of blue
barrel~ full of ore is carried out in broad daylight at the airports of Niamey and
Agadez or in the port of Cotonou (Benin). Moreover, the quantities which will be
sold to each of the customers is known i.n advance, by decree. Thus for exports
which will be delivered this year: France will purchase 2,293 tons (as compared
with 1,344 in 1980 or 47 percent of Cotal sales); Libya, 1,212 tons (25 percent);
Japan, 816 tons (17 percent); Spain, 300 tons (6 percent); the FRG, 125 tons
(3 percent) and Iraq 100 tons (2 percent). In total: 4,846 tons for 1980. In
fact, to boycott some purchaser or other according to the whims of western diplomacy
would be tantamount for the Nigerien Government to losing control of the receipts
of foreign exchange vital for the pursuit of economic development [Text] [Paris
JEUNE AFRIQUE in French NB 1080, 16 Sep 81 p 31) [COPYRIGHT: Jeune Afrique GRUPJIA
i9si~
JAPANESE URANIUM EXPLORATION AGREE1~3dT--A Japanese company, the Power Reactor and
Nuclear Fuel Development Corporation [PNC], signed on 9 September in Niamey a draft
agreement with the Nigerien Office of Mineral Resources [ONAREM] for the exploration
and exploitation of a new uranium depo~it. The ONAREM-PNC association is to start
- soon its exploration in Agadez Department (nor~hern Sahara), on the In Adrar site.
The draft agreement was signed for the Nigerien side by the minister of mines,
Annau Mahamane, the director of ONARF.~I, Sani Koutoumbi, and by the director of the
PNC, Mikio Isetani. It stipulates that the Japanese company will finance the
explorati~n and installations at the rate of 400 million CFA francs for the next
2 years and an additional 600 million C~A francs for the fourth year. Japan is
already active in Niger in the exploration and exploitation of uranium in particular
through the Overseas Uranium Resources Development [OURD], which holds 25 percent
of the capital of the Akouta Mining Company [COMINAK], one of the two large Nigerien
uranium exploitation enterprises, with the Air Region Mining Company [SOMAIR].
Japan has purchased in Niger 816.6 tons of uranium since the beginning of the year.
(Text] [Daris MARCHES TROPICAUX ET MEDITERRANEENS in French No 1871, 16 Sep 81
p 2383] [COPYRIGIiT: Rene Moreux et Cie Paris 1981]
CSO: 4719/29 ENn
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