Official data on mean effective doses from external and internal exposure to the residents of the settlements of the Bryansk, Kaluga, Oriol, Tula, Ryazan and Lipetsk oblasts of the Russian Federation are given in the special issue. The doses are listed for the accumulation during the first year following the accident at the Chernobyl NPP and for the accumulation during the period from 1986 through 1995. For those who had lived in the “control” territories of the Bryansk oblast and afterward had been relocated to the “clean” territories from 1986 through 1992, the doses accumulated from the time of radioactive contamination to the time of relocation were estimated.
The
doses received by residents of the settlements of the Bryansk, Tula and Oriol
oblasts were estimated by the specialists of the Institute of Radiation Hygiene
of the Ministry of Public Health of the Russian Federation (St.Petersburg), the
doses in the Kaluga oblast were estimated by specialists of the Medical
Radiological Research Center of Russian Academy of Medical Sciences, the doses
in the settlements of the Ryazan and Lipetsk oblasts were estimated by
specialists of the State Scientific Center of the Russian Federation -
Institute of Biophysics.
The
dose was estimated in line with the methodological recommendations 2.6.1.579-96
“Reconstruction of mean effective doses accumulated by the residents of the
settlements of the Russian Federation for the period from 1986 through 1995 due
to the accident at the Chernobyl NPP in 1986” approved by the
Goskosanepidnadzor (originally called the State Committee for Sanitary and
Epidemiological Surveillance, now called the Department for State Sanitary and
Epidemiological Surveillance of the Ministry of Public Health of the Russian
Federation) in 1996. The results of the estimation were discussed and adopted
at the session of the Russian Scientific Commission on Radiation Protection.
Mean
accumulated effective doses were estimated in those settlements of the Bryansk,
Kaluga, Tula, Oriol oblasts where the average density of soil contamination by 137Cs
was more than 37 kBq/m2 (1 Ci/km2).
The
estimates are addressed to the institutions and the bodies of the
Gossanepidnadzor of the Ministry of Public Health of the THE RUSSIAN
FEDERATION, as well as to practical workers and other specialists involved in
the analysis of the consequences of the Chernobyl accident.
The
currently published estimates of the effective doses can be used for making managerial
decisions, if so desired by the Gossanepidnadzor of the Ministry of Public
Health of Russia.
The details of the recommendations MU 2.6.1.-96 must be taken into account when the estimates given in the tables of the issue are used.
The Editorial Board believes that the publication of the estimates will be helpful for scientists, officials, practical workers of health-care institutions and centers functioning under auspices of Gossanepidnadzor of Russia. Information of such detail, volume and character have never been published before in Russia. They should also be of interest to western scientists wishing to understand the extent of the Chernobyl disaster.
Brief analysis
of the calculated mean effective doses, which had been accumulated by the
residents of the settlements of the Russian Federation affected by
radioactive contamination due to the accident at the Chernobyl NPP in 1986
for the period from 1986 through 1995
The
contamination of the territory of Russia with radioactive materials due to the
Chernobyl accident started on April 28, 1986 as a result of changing the
direction of the wind blown over the Chernobyl area to the northeast on April
27, 1986. Due to the intensive rainfall over the boundary between the Mogilev,
Gomel oblasts of Belarus and the Bryansk oblast of Russia that occurred on
April 28-29, 1986 when the radioactive cloud moved over the territory, the
Bryansk-Belarus "spot" was formed (1, 5). On average, one day later,
on April 29-30, radionuclides were deposited in a similar way and probably from
the same cloud in the territory of Kaluga, Tula and Oriol oblasts. The maximum
level of the radioactive contamination of the territory in the
Tula-Kaluga-Oriol "spot" was lower by an order of magnitude than that of the Bryansk-Belarus
"spot". It is suggested that was due to the extension and exhaustion
of the cloud as a result of previous depositions (1, 4-8). Nevertheless, the
level of radiation exposure to the population of the three oblasts especially
in 1986 had been taken into account by the national and local authorities when
decisions concerning radiation protection were made. The decisions were based
on information from intensive radiation monitoring carried out from May 1986 by
central and local bodies and institutions affiliated to Goskomgidromet of the
USSR (State Committee of Hydrometeorology of the USSR), Ministry of Public
Health of the Russian Federation and Gosagroprom (State Committee of
Agricultural Industry) (1, 2, 4, 8, 9).
From
the beginning of the radioactive fallout the population was exposed to external
and internal radiation from a mixture of various fission products and
activation products. Radioisotopes of iodine and cesium, as well as strontium
and plutonium, were the most significant contributors. Radiation monitoring
involved the estimation of the density of contamination of the soil by
long-lived radionuclides, such as 137Cs, 90Sr and
isotopes of plutonium, in the settlements and surrounding territories. Their
concentration in air was measured as well. The radionuclide composition was
studied, the dose rate from g-radiation was
measured, foodstuffs and water were tested for existence of radioactive
radionuclides, and content of radionuclides in a human body was measured. All
this information enabled one to estimate the current annual doses to the
population. This estimate was necessary for making decisions. It was very
difficult to estimate radiation doses that accumulated in the first year after
the accident. At that time dozens of radionuclides were sources of radiation,
each of which had different radiological properties. Temporal changes of the
radiation situation were rapid and depended on local environmental and social
conditions (1-5, 7-9).
Table
1 consists some important characteristics of the radionuclides that arrived at
the territory of the Russian Federation as a result of atmospheric transfer.
Table 1. Characteristics of the principal radionuclides deposited to the territory of Russia following the Chernobyl catastrophe (7, 10).
|
Radionuclide |
Half-period |
|
||||
|
Mother |
Type of radiation |
Daughter |
Type of radiation |
Tm |
Td |
|
|
137Cs |
b |
137mBa |
b+g |
30.2 g |
2.55 min |
137Ba |
|
136Cs |
b+g |
- |
|
13.1 day |
- |
136Ba |
|
134Cs |
b+g |
- |
|
2.06 g |
- |
134Ba |
|
131I |
b+g |
- |
|
8.04 day |
- |
131Xe |
|
132Te |
b+g |
132I |
b+g |
78.2 h |
2.3 h |
132Xe |
|
133I |
b+g |
133Xe |
b+g |
20.8 h |
5.25 day |
133Cs |
|
140Ba |
b+g |
140La |
b+g |
12.74 day |
40.27 h |
140Ce |
|
95Zr |
b+g |
95Nb |
b+g |
63.98 day |
35.15 day |
95Mo |
|
103Ru |
b+g |
103mRh |
b+g |
39.28 day |
56.1 min |
103Rh |
|
106Ru |
b |
106Rh |
b+g |
368.2 day |
3 s |
106Pd |
|
141Ce |
b+g |
- |
|
32.5 day |
- |
141Pr |
|
143Ce |
b+g |
143Pr |
b+g |
33 h |
13.56 day |
143Nd |
|
144Ce |
b+g |
144Pr |
b+g |
284.3 day |
17.3 min |
144Nd |
|
125Sb |
b+g |
125mTe |
b+g |
2.77 g |
58 day |
125Te |
|
99Mo |
b+g |
99mTc |
b+g |
66 h |
6.04 h |
99Ru |
At the end of the decade after the Chernobyl accident the development of recommendations for reconstruction of the dose accumulated by the population for the whole period of exposure was completed. The document “Reconstruction of the mean effective dose to the population of the settlements of the Russian Federation affected by radioactive contamination as a result of the accident at the Chernobyl NPP that had been accumulated during the period 1986-1995” was developed in 1996 by specialists of the Institute of Radiation Hygiene of the Ministry of Public Health of the Russian Federation (St.-Petersburg), Medical Radiological Research Center of Russian Academy of Medical Sciences, State Research Center of the Russian Federation - Institute of Biophysics, Scientific and Productive Association “Typhoon” of Roshydromet (10). The document (10) was approved as methodical recommendations 2.6.1.579-96 by the Department of Goskomsanepidnadzor of the Ministry of Public Health of Russia.
The mean accumulated effective dose in the settlements of the Bryansk, Oriol and Tula oblasts of Russia was calculated by specialists of the Institute of Radiation Hygiene of the Ministry of Public Health of the Russian Federation (St.-Petersburg) (composition of the team of specialists was given below); in the settlements of the Kaluga oblast the calculation was made by the specialists of the Medical Radiological Research Center of the Russian Academy of Medical Sciences, the specialists of the State Research Center of the Russian Federation (Institute of Biophysics) calculated doses in Ryazan and Lipetsk oblasts.
The
mean accumulated effective doses were calculated for residents of 1091
settlements of the Bryansk, 1489 settlements of the Tula, 1038 settlements of
the Oriol and 404 settlements of the Kaluga oblasts. According to reports of
the Goskomhydromet in these settlements the mean density of soil contamination
with 137Cs exceeded 37 Bq/km2 (1 Ci/km2). No
limitations for the level of density of soil contamination with 137Cs
were made for the calculation of the dose in 721 settlements of the Ryazan and
142 settlement of the Lipetsk oblasts.
Mean
accumulated effective dose were estimated in order to justify the preventive
measures addressed to the population which were based on the “Concept for
radiation, medical and social protection and rehabilitation of the accidentally
exposed population of the Russian Federation” (11). The important task of the
job was to deliver the information on radiological consequences of the
Chernobyl accident to the population and local authorities. This was done.
With some limitations the estimated mean accumulated effective dose can be applied to the prognosis for delayed health effects of the Chernobyl accident on the population of the affected oblasts of the Russian Federation. It is important to note that the thyroid dose from radioiodine was not included in the calculation of the mean doses that are given in the tables.
Method for
dose reconstruction
General information
The models and algorithms for the calculation of
doses accumulated by residents are based on experimental investigations
conducted over many years in the settlements of Bryansk, Tula, Oriol and Kaluga
oblasts of Russia. These are the oblasts with the highest concentration of
radionuclides after the Chernobyl accident (2, 9,12-16). The reconstruction of
the mean accumulated effective dose (MAED) in the years 1986-1995 by the
residents of six oblasts of Russia has been accomplished according to the
Methodical Recommendations of Minzdrav (Ministry of Public Health) of the
Russian Federation (THE RUSSIAN FEDERATION) (MY 2.6.1.579-96) which determine
the requirements of the basic data and of the calculational procedure for
estimating MAED of residents of the settlements of Russian Federation exposed
to radionuclide contamination from the Chernobyl NNP accident of April 26, 1986
(10).
The
mean accumulated effective dose (MAED)
averaged over all residents of the settlements is calculated in a
conservative way as the mean dose accumulated by the adult population. It was
found in earlier dosimetric investigations of residents living near Chernobyl,
that the mean dose accumulated in a year by children of various ages did not
exceed that of the adult population of the same settlement. The only exception
is the dose accumulated in the thyroid, which is due to I-131, and which is higher in children than in the
adult population of the same settlements. The dose reconstruction in the
thyroid is calculated according to a
special procedure documented by the Minzdrav of the Russian Federation.
According to these “recommendations”
the mean effective accumulated dose (E) is equal to the sum of the dose due to
external gamma radiation Eext and the dose due to internal
irradiation Eint:
E = Eext + Eint
The radiation monitoring data in 1986-1995 that was conducted in the
regions of radioactive contamination due to Chernobyl accident has been used in
calculation of MAED. Measures undertaken for the resident protection were taken
into consideration. The external radiation dose had been reduced by the special
engineering measures in the controlled
territory of the Bryansk region. The internal irradiation dose had been
diminished by special delivery of “radiation clean” foodstuffs (milk, meat etc)
to the controlled Bryansk oblast, by a prohibition to eat “home” animals and
homegrown foodstuffs, and by special measures undertaken in agriculture farms
in Bryansk, Tula, Kaluga and other regions of the Russian Federation.
In
appendixes to MY 2.6.1.579-96 made for several regions of the Russian
Federation some peculiarities of the radionuclide contaminations of these
regions are listed: the date of radionuclide sediments, their isotope
composition, the list of contaminated settlements and figures on density of
contaminations by Cs-137 and Sr-90 gathered by “Rosgidromet” as well as
information on the volume of monitoring of surroundings and of foodstuffs, on
measurements of radionuclide concentration in the bodies of the residents and
on individual doses of external gamma irradiation.
The
radionuclide monitoring data
The
database used to reconstruct MAED of the internal and external irradiation of
residents of settlements in six oblasts of the Russian Federation for 1986-1995
contain the following information:
. names of regions, villages and
settlements, types of settlements and number of residents in each of them
according to the1989 census or according to data obtained in the
years1985-1986,
. the distribution of residents in
different types of buildings (made of wood, one-story buildings, made of brick,
many-floor buildings);
. distribution of village and town
residents between different social occupations and professions,
. distribution of farms according to
the types of soil;
. the times of the beginning and the
end of the deposition of radionuclides sediments from the Chernobyl accident in 1986 (10),
. isotopic composition of the
radioactive deposition in the oblast or region up to the end of deposition in
April 1986 (10)
.
the mean density of soil contamination by Cs-137 and Sr-90 in the
settlements as it was measured by 1.01
96 (according to “Rosgidromet”(8)),
. data obtained of more than 150,000
measurements of cesium isotopes and Sr-90 content in home made foodstuffs
(milk, potatoes etc.),
. data obtained in more than 300
thousand counter measurements of Cs-137,-134 concentration in the bodies of the
residents.
Dose of external gamma-irradiation
The external irradiation dose Eext,
includes doses from all deposited radionuclides with lifetimes from
several hours to 30 years (Table 1) whose contribution to the dose received in
10 years is bigger than 0.1%. The effective dose of b- and g-
irradiation obtained from radioactive clouds moving over the settlements of the
Russian Federation, according to model estimates, is less than 5% of that
accumulated during the first year after the accident and is not taken into
account in this paper. According to model calculations, the effective dose
received from distant and contact irradiation of skin by b-irradiation
of radionuclides is small and is not taken into account either
The
mean received effective dose by external irradiation of residents in each
considered settlement was calculated for the first year after the accident and
for following years (up to the end of
1995).
The
equation for the effective dose rate during the first year after the accident
was calculated by the formula

mkSv/day,
where i is the
number of adults in a particular group;
dD(t)/dt is the dose rate received in the air at the height of 1 meter
above an open virgin strip of
ground, mkGy/day;
CE is the transition coefficient from
the dose received in the air to the dose of adult people. It is equal to 0.75
mkSv/mkGy;
KC
is a
coefficient describing the reduction of effective dose by the snow layer. It is
equal to 0.8 for the time interval from November 1 to March 31 and to 1 for all
other months;
Lj
takes into
account the difference between virgin ground and the typical
ground in the settlement;
The sum is take over all
radionuclides j
Fij is part of time when residents of
group i spend in j-type part of the settlement. The Lj
and Fij values are given in (10) for various seasons of
the first post-accident year.
When
calculating the dose from external irradiation for the second time interval
(1<t<9.7 years), we only took into account the gamma radiation from
Cs-137 and Cs-134. The contribution of gamma radiation of all other
radionuclides (Ru-106 ~ 1%, Sb-125 ~ 1%) was neglected. The dose changes very
slowly with time, and we only used year-averaged values of Fij for
the calculations.
We used in the
calculations official demographic data on the number of residents living in
houses of different types. In the villages we considered two types of buildings
only: one-story buildings made of wood and of brick. If there were many-floor
houses we considered the doses as if their residents lived in one-story
buildings. In town-like settlements and in towns the part of the residents
living in many-story buildings had been taken into account.![]()
To make the calculations easier, we calculated the following
specific values of mean effective doses of external irradiation
[mkSv/(kBq*m-2)
for Cs-137] for the residents of three types of settlements:
for village settlements
. dose accumulated during the first
year after the accident,
. dose accumulated during next years
(up to 1995) if the engineering deactivation is not taken into account;
. dose accumulated during next years
(up to 1995) if the engineering deactivation is taken into account (for
Briansk oblast only);
for town-like settlements
. dose accumulated in the first year
after the accident;
. dose accumulated during next years
(up to 1995)
for towns
. dose accumulated in the first year
after the accident;
. dose accumulated during next years
(up to 1995)
For several resettled
settlements in Gordeevsk, Zlynkov, Krasnogorsk and Novozybkov regions of
Bryansk oblast the data had been calculated up to the time of resettlement:
09.01. 1986 for Barsuki, Progress, Knyazewschina, and Nizhnyaja Melnica in Krasnogorsk region, and up to 01.01.1990 or
01.01.1992 for other 40 villages, according to Bryansk oblast administration
data.
Internal irradiation dose
The algorithms used for
reconstruction of the internal dose are different for the first year after the
accident (04.29.86 – 04.30.87) and for the next time period because of the
different formation processes. The doses are caused by 134Cs, 137Cs,
90Sr and 89Sr that mostly enter with homemade foodstuffs.
In the first period,
during the first two to four months after the Chernobyl accident, the level of
“surface" contamination of vegetable and animal foodstuffs by the j-th
radionuclide contamination in the middle strip of Russia was, mostly, connected
with the density sj of soil contamination by this
isotope and by meteorological factors of its deposition. The concentration of
the j-th radionuclide of cesium and strontium Cjm in the milk of cows grazing in contaminated
districts can be approximately calculated by the formula:
Cjm(t)
= KPjm(0)*sj(t)*(exp(-ln2*t/T2)-exp(-ln2*t/T2)),
Bq/l,
Where KPjm(0) is the initial (at t=0) coefficient of the
transition of the of j-th isotope into cow's milk after contamination of
the surface soil and of vegetables, m2/kg(l);
T1= 2 d is the half-life
of cesium and strontium removal from cow's milk.
T2 =15 d is the half-life
of removal of contamination from the vegetables that comprise cow food.
![]()
Beginning in autumn 1986 and
for a long time there afterwards, the main significance of the radionuclide
transition into vegetables was through their root system. The dependence of
“root” KP on the type and on agrochemical characteristics of the soil where
foodstuffs and animal food is grown had been established. On turf-podzol soils,
the “root” KP of Cs-134,-137 into vegetable and animal foodstuffs diminished
during the years 1986-1991 with 1-1.5 year period. Beginning in 1991-1992 the
KP of Cs-134, -137 became gradually smaller and in 1993-1995 was not observed
at all. Beginning in 1987 the Sr-90 transition coefficient into foodstuffs
diminished with a 5-7 year period.
In
all internal dose calculations we prefer those based on SICH data. The quantity
of these measurements was especially large during the first 5 years after the
accident when the main contribution to the total dose was accumulated. When these
data are absent or insufficient, the dose is estimated from the data on
radionuclide content in foodstuffs responsible for the main contribution to
dose (milk and potatoes). If their quantity is inadequate or if they are not
reliable, the radioecological model must be used. This model is based on
transition coefficients of radionuclides from soil into foodstuffs (10).
According
to the Methodical Recommendations (10), in dose calculations for residents of
towns of oblast or region subordination (TOS) and (TRS) and of (TLS) the data
obtained in SICH measurements are preferable and if they are absent the data
are used which are obtained in analyses of milk and potatoes in the shops (TOS)
and in small private farms (TRS and TLS).
If these data are absent as well, it is considered that town and TLS
residents consume foodstuffs with the same radionuclide content as in
agricultural settlements of the region.
The internal irradiation
doses of the residents during the period from the second to the tenth years after
the accident had been calculated by summation of year doses due to local
foodstuff consuming containing radionuclides of three types: Cs-137, Cs-134 and
Sr-90. The program of computer calculations for every year looked first for the
data of SICH measurements. If these data were absent it looked for data of
Cesium and Strontium radionuclide content in local foodstuffs. If the measured
data were enough in one year, they were used for that year and also for the
previous and for the following years. If the data of both types did not contain
information needed for calculations, the program takes the data on soil type
used for farming and estimates coefficients of radionuclide transition into
milk and potatoes using the data of the table 3.2 of reference (10).
Table 2 gives summarized
data related to 6 contaminated oblasts of the Russian Federation, in which mean
accumulated effective doses have been already calculated.
It is seen from the table 2 that in about
50% or more (Ryazan and Lipetsk oblasts respectively) of the dose accumulated
during 9.7 years had been accumulated during the first year after the accident.
The ratio between maximal and minimal values of the mean accumulated effective
dose is ranged between 14 (the Oriol oblast) and 42 (the Bryansk oblast).
Estimates of the dose values show that in
the Bryansk oblast the mean dose accumulated during the 9.7 years is within the
range of 4 mSv to 167 mSv. In 27 settlements the accumulated dose exceeded 70
mSv, which value has been proposed as a criterion for the estimation of the
degree of the radiation effect on the population. In the Tula oblast there was
not one settlement with a mean accumulated effective dose above 70 mSv. In one
settlement of the Arsenievsky rayon of the Tula oblast the mean dose
accumulated for 9.7 years was only 33 mSv. In 160 settlements of that oblast
the mean accumulated effective dose is within limits of 10 mSV to 30 mSv. In
the Oriol oblast there was not a settlement with accumulated effective dose
that exceeded 30 mSv.
In the settlements of
the Kaluga oblast the maximum value of the mean effective dose accumulated for
9.7 years after the accident is 25 mSv. In the Ryazan and Lipetsk oblasts the dose
is considerably less than that in the other oblasts given in Table 2. However,
the doses averaged for a settlement of all of the oblasts, except for the
Bryansk oblast, distinguish at the less extent. More details concerning the
value of mean accumulated effective dose to the adult population of the
settlements are given in relevant tables of this issue.
Table 2. Summary of the results of the
calculation of the mean effective doses in contaminated oblasts of the Russian
Federation accumulated in the first year after the accident and during the 9.7
years subsequent to the accident at the Chernobyl NPP.
|
|
|
Mean
effective dose accumulated |
Mean
effective dose accumulated |
||||||
|
|
|
|
Standard
deviation |
|
|
|
Standard
deviation |
|
|
|
Bryansk |
1091 |
11.4 |
9.5 |
2.4 |
80 |
23.5 |
19.2 |
4 |
167 |
|
Kaluga |
404 |
3.0 |
2.3 |
0.7 |
12 |
6.3 |
4.9 |
1.4 |
25 |
|
Tula |
1489 |
2.6 |
1.5 |
0.7 |
10.4 |
5.5 |
3.7 |
1.6 |
33 |
|
Oriol |
1038 |
2.2 |
0.9 |
0.7 |
8.1 |
4.4 |
2.5 |
1.7 |
23 |
|
Ryazan |
721 |
2.4 |
1.2 |
0.2 |
8.0 |
3.9 |
1.9 |
0.3 |
9.8 |
|
Lipetsk |
142 |
2.1 |
0.8 |
0.3 |
5.1 |
3.2 |
1.1 |
0.4 |
7.9 |
The work was carried out in
1995-1997 on the basis of contracts granted by the Ministry of Emergency of
Russia and the Ministry of Public Health of Russia.
The teams of experts who estimated the mean
accumulated effective dose were:
Bryansk, Tula and
Oriol oblasts:
Institute of Radiation
Hygiene of the Ministry of Public Health of Russia (St. Petersburg)
Prof. P.V.Ramzaev, Director
Dr. M.I.Balonov, Head of Department; Dr.
V.Yu.Golikov, Leading Researcher; Dr. G.Ya.Bruk, Leading Researcher; Dr.
V.N.Shutov, Head of Laboratory; Dr. A.B.Bazyukin, Senior Researcher; Dr.
I.A.Zvonova, Leading Researcher; Dr. I.G.Travnikova, Leading researcher; Dr.
T.V.Zhestko, Researcher; Mr. A.Yu.Vlasov, Researcher
Branch of the
Institute of Radiation Hygiene of the Ministry of Public Health of Russia (Town
of Novozybkov, the Bryansk oblast)
Dr. V.I.Kovalenko, Director
Dr. V.I.Parkhomenko, Head of Department; Dr. M.V.Kislov,
Senior Researcher; Dr. A.V.Ponomarev, Senior Researcher
Central Department of
Epidemiological Surveillance of the Bryansk oblast
Dr. P.A.Stepanenko, Chief Physician
Dr. E.N.Shaposhnikova, Head of the Department of Radiation
Hygiene; Dr. I.S.Kaplun, Chief Physician of the Novozybkov branch; Dr.
V.A.Vasilevitsky, Hygienist of the Novozybkov branch; Dr. O.P.Ignatova, Chief
Physician of the Klintsy branch; Dr. S.E.Krivenko, Hygienist of the Klintsy
branch
Dr. A.G.Lobkovsky, Chief Physician
Dr. D.S.Kotik, Head of the Department of Radiation Hygiene;
Dr. A.S.Kornilov, Hygienist
Dr. Yu.A.Odintsov, Chief Physician
Dr. S.A.Milovanov, Head of the Department of Radiation
Hygiene, Dr. S.N.Poteyev, Hygienist
Kaluga oblast:
Academician of RAMS A.F.Tsyb, Director
Dr. V.A.Pitkevich, Head of Laboratory; Dr. O.K.Vlasov,
Leading Researcher; Dr. I.K.Khvostunov, Senior Researcher; Mrs. N.V.Shchukina,
Researcher
Ryazan and Lipetsk
oblasts:
Academician of RAMS L.A.Ilyin, Director
Dr. M.N.Savkin, Deputy Director; Dr. M.P.Grinev, Head of
Department; Dr. A.V.Titov, Senior Researcher; Dr. A.N.Lebedev, Senior
Researcher; Dr. A.V.Gordeyev, Senior Researcher.
Mrs. G.S.Perminova, Head of Department
1.
Israel
Yu.A., Vaculovsky S.M., Vetrov V,A. and others: Radioactive contamination of
natural environments. Edited by Yu.A. Israel. Leningrad, Gidrometeoizdat, 1990
(in Russian)
2.
Medical
aspects of Chernobyl accident. Kiyv, Zdorovje. 1988,232 p. (in Russian)
3.
Sources,
effects and risks of ionizing radiation. Annex D. Exposures from Chernobyl
accident. UNSCEAR, 1988, Report, United Nations, New York, 1988.
4.
International
Chernobyl Project. Technical report. Estimation of radiological consequences
and protective measures IAEA, VIENNA, 1992, 740 p.
5.
The
Chernobyl papers. V.I. Doses to the Soviet
Population and early Health Effects. Studies Ed. By S.E.Merwin and M.I
Balonov, Research Enterprises, Richland, 1993, 440 p.
6.
Ilyin
L.A.. Balonov M.I. at al (1990) Radiocontamination Patterns and possible health
consequences of the accident at the Chernobyl nuclear power station. J. Radiol.
Prot. 10, pp.3-29
7.
Pitkevich
V.A. Shershakov V.M., Duba V.V., Chekin S. Yu., Ivanov V.K., Vakulovski S.M.,
Mahonko K.P., Volokitin A.A. Tsaturov Yu.S., Tsyb A.F. Reconstruction of the
composition of the Chernobyl radionuclide fallout in the territories of
Russia. Radiation & Risk, 1993,
issue 3, pp. 39-70.
8.
Data
on settlement contamination in Russia regions by Cs-137, Sr-90 and Pu. Computer
base. Rosgidromet, 1996.
9.
Reference
book on radiation conditions and radiation doses for population of different
regions of Russian Federation due to Chernobyl accident. Edited by M.I.Balonov,
S.Peterburg, 1993, 147 p. (in Russian)
10.
Methodical
Recommendations. M.R. 2.6.1.579-96. Effective irradiation dose reconstruction
for residents of Russian Federation settlements exposed to radioactive
contamination due to Chernobyl accident in 1988 y. Official edition. Minzdrav
of Rusia. Moscow,1996
11.
Radiation,
medical and social protection and rehabilitation of residents of Russian
Federation exposed to accidental irradiation. RNKRZ, 1995
12.
Shutov
V.N. Bruk G.Ya, Balonov M.I, Parkhomenko V.I., Pavlov I.Yu. Cesium and
strontium radionuclid migration in the agricultural ecosystem and estimation of
internal Doses to the population. In Chernobyl Papers. Vol.1.Ed.by
S.E.Mervin and M.I. Balonov, Research Enterprises, Richland,
pp. 167-218, (1993).
13.
Balonov
M.I., Bruk G.Ya..Golikov V.Yu, Yorkin V.G., Zvonova I.A., Parkhomenko
V.I.,Shutov V.N. Exposure of the population of Russian Federation as a result
of the
Chernobyl accident. Radiation & Risk. issue 7,
Moscow-Obninsk, 1996, pp. 8-39.
14.
Determination
of 1996-1998 year mean effective irradiation dose of the residents of Russian
Federation due to Chernobyl Accident. MR 2.6.1.547-96. Second amendment To
Methodic Recomendations GKCEN THE
RUSSIAN FEDERATION MR 2.7.001-93 made
at March 12 1993.
15.
Pathway
analysis and dose distribution. Report for
JSP-5 Ed. By P.Jacob and I. Liktarev (1996) EUR 16541 EN Luxembourg, 130
pp.
16.
V.Yu
Golikov, M.I. Balonov and A.V. Ponomarev (1993) Estimation of External
Radiation Doses to the population After Chernobyl accident. In The Chernobyl
Papers, vol.1, Doses to the Sovjet Population and Early Health Effects Studies.
Ed. by S.E.Mervin and M.I.Balonov, Richland, Research Enterprises, pp. 247-288.