Mathematical simulation of “Shelter” object releases impacts
Methods of mathematical modeling of radiological human impacts are described. Calculation of admissible
 releases at different exploitation stages of New Safe Confinement at the existing ChNPP “Shelter” object are given. Описано методику математичного моделювання впливів на населення за всім...
Збережено в:
| Опубліковано в: : | Вопросы атомной науки и техники |
|---|---|
| Дата: | 2004 |
| Автори: | , , , , |
| Формат: | Стаття |
| Мова: | Англійська |
| Опубліковано: |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2004
|
| Теми: | |
| Онлайн доступ: | https://nasplib.isofts.kiev.ua/handle/123456789/80556 |
| Теги: |
Додати тег
Немає тегів, Будьте першим, хто поставить тег для цього запису!
|
| Назва журналу: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Цитувати: | Mathematical simulation of “Shelter” object releases impacts / V.G. Batiy, S.A. Paskevich, V.M. Rudko, A.A. Sizov, V.N. Shcherbin // Вопросы атомной науки и техники. — 2004. — № 5. — С. 96-100. — Бібліогр.: 4 назв. — англ. |
Репозитарії
Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860086725886345216 |
|---|---|
| author | Batiy, V.G. Paskevich, S.A. Rudko, V.M. Sizov, A.A. Shcherbin, V.N. |
| author_facet | Batiy, V.G. Paskevich, S.A. Rudko, V.M. Sizov, A.A. Shcherbin, V.N. |
| citation_txt | Mathematical simulation of “Shelter” object releases impacts / V.G. Batiy, S.A. Paskevich, V.M. Rudko, A.A. Sizov, V.N. Shcherbin // Вопросы атомной науки и техники. — 2004. — № 5. — С. 96-100. — Бібліогр.: 4 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Methods of mathematical modeling of radiological human impacts are described. Calculation of admissible
releases at different exploitation stages of New Safe Confinement at the existing ChNPP “Shelter” object are given.
Описано методику математичного моделювання впливів на населення за всіма можливими шляхами у
результаті можливого викиду радіоактивних речовин. Надано результати розрахунку допустимих викидів на
різних етапах експлуатації нового безпечного конфайнменту над існуючим об’єктом “Укриття”
Чорнобильської АЕС.
Описана методика математического моделирования воздействий на население по всем возможным путям
в результате возможного выброса радиоактивных веществ. Приведены результаты расчета допустимых
выбросов на различных этапах эксплуатации нового безопасного конфайнмента над существующим
объектом “Укрытие” Чернобыльской АЭС.
|
| first_indexed | 2025-12-07T17:20:19Z |
| format | Article |
| fulltext |
MATHEMATICAL SIMULATION
OF “SHELTER” OBJECT RELEASES IMPACTS
V.G. Batiy, S.A. Paskevich, V.M. Rudko, A.A. Sizov, V.N. Shcherbin
Interdisciplinary Scientific and Technical Center “Shelter” of Ukraine’s NAS
e-mail: batiy@mntc.org.ua
Methods of mathematical modeling of radiological human impacts are described. Calculation of admissible
releases at different exploitation stages of New Safe Confinement at the existing ChNPP “Shelter” object are given.
PACS: 28.41Te
1. INTRODUCTION
During practical activities aimed at operation of New
Safe Confinement (NSC) of ChNPP “Shelter” object,
diverse works are planned to carry out (dismantle of
unstable structures, subsequent retrieval of fuel-
containing materials, et al.), which can be resulted in
radiation impacts to public and environment. In force of
the fact that the NSC will contain a huge amount of
nuclear and radioactive materials, it can be referred to
radiation hazardous facilities.
In conformity with NRBU-97, limitation of public
exposure is implemented by way of regulating and
monitoring of aerosol releases and water discharges in
the course of operating radiation and nuclear facilities.
To reduce the releases, admissible release (AR) of
radioactive substances into environment must be
established, which refers to radiation and hygienic
regulations of first group.
To solve that task, NSC release modeling must be
conducted and impact of these releases to the public
should be estimated. Besides, one should identify the
critical group of public (i.e. groups, impact on which
will be maximal), as well as impact ways that are most
intensive in influencing a critical group.
AR was evaluated from the condition of non-exceeding
relevant release quotes due to all the ways of dose
formation (40 µSv/year) at 10 km distance from NSC.
2. PROCEDURE FOR RELEASE IMPACT
ESTIMATE
To identify release impacts to public, one should
estimate effective dose of human exposure with
considering all dose formation ways.
There are the following main release impacts to a man:
• internal exposure conditioned by radioactive
substance intake to human organism with food;
• internal exposure due to radioactive substance
inhalation;
• external exposure from radionuclides precipitated on
the earth;
• external exposure conditioned by staying in
radioactive cloud.
The following foodstuff makes the basis for man’s
food allowance: potable water; bread; potato; cabbage;
fruits and berries; leaf vegetables; meat and its
processing produce; milk; fish.
3. RADIOACTIVE SUBSTANCE
CONCENTRATIONS IN THE AIR AND SOIL.
CONTINUOUS RELEASES
As release cloud moves, radioactive aerosol
precipitate on earth surface. Surface source of external
exposure is formed. Radionuclide precipitation density
on the soil after release Q (Bq/s) is defined from the
formula [1]:
)( Z
gs GGvQA Λ+=
•
, (1)
where Q – release intensity, Bq/s ; gv – dry
precipitation velocity, m/s; G – meteorological dilution
factor, s/m3, under which is implied the ratio of
volumetric activity of radionuclide in atmosphere to a
release per time unit; Λ – wash-out constant, 1−s ,
depending on precipitation type, raindrop spectrum,
precipitation intensity; zG – integral of dilution factor
G along vertical coordinate z, s/m3,
Ikkr 0=Λ , (2)
where I – precipitation intensity, mm/hour; 510−=rk
hour/(mm · s) – standard value of absolute rain
washing-out ability (for all nuclides beside inert
gases), specific for rain intensity I = 1 mm/hour; 0k –
relative washing-out ability for diverse precipitation
types (see Table 1).
∫=
zH
z dzzyxGyxG
0
),,(),( , (3)
where zH – height of cloud lower boundary –
precipitation source (m).
Table 1. Relative washing-out ability for diverse
precipitation types [1]
Precipitation type 0k
Rain 1,0
Rain with thunderstorm 1,1
Snow with thunderstorm 2,4
Rainfall 2,8
Snow 3,0
Drizzle 4,5
Mist 5,0
96 PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2004, № 5.
Series: Nuclear Physics Investigations (44), p. 96-100.
Rough estimate of meteorological dilution factor in
vicinity and at up to 10-km distance behind the zone of
near-surface concentration maximum can be made using
the procedure of envelope:
xuhe
xFG )(
)2(
2
2/3
η⋅
π
= , (4)
where η – wind rose oblongness in specified direction;
)(xF – cloud exhaustion function; h – release source
height, m; u – wind average velocity, m/s; x – distance
from a man to release source.
This formula gives maximum (conservative)
estimates in the sense, that under any law of vertical
dispersion factor change and any reiteration of weather
conditions, no high concentration values can be
obtained.
Wind rose oblongness in specified direction is
defined by the following formula:
0/ nn=η , (5)
where n and 0n – wind direction reiteration in a given
azimuth sector under real wind rose and under round
wind rose, accordingly.
Function of radioactive cloud exhaustion as result of
dry precipitation is defined by the following formula:
,
2
exp1exp)(
0
2
2
σ
−⋅
σ
⋅−= ∫
x
zz
dxhAxF (6)
where )(/()/2( huvA g⋅π= ; )(hu – horizontal
constituent of wind velocity in dependence of effective
release height, m/s; zσ – mean-square deflection of
admixture distribution in release cloud due to turbulent
diffusion in vertical direction, m;
phuhu )2/()2()( ⋅= , (7)
where )2(u – wind velocity at 2 m height, m/s; р –
factor from Table 2.
Table 2. Exponential factor values р for wind velocity
estimate
Air stability category using Pasquill
A B C D E F
Standard
conditions 0,07 0,07 0,10 0,15 0,35 0,55
Urban
conditions 0,15 0,15 0,20 0,25 0,40 0,60
Dispersion factors σz are defined in dependence of
weather conditions using Smith-Hosker formula:
>
≤
=
,)x(g)x,z(f,
;)x(g)x,z(f),x(g)x,z(f
)x(
max
z
max
z
max
z
z σσ
σ
σ
0
00 (8)
where max
zσ – limiting value zσ for given category of
atmospheric stability; 0z – height of underlying surface
roughness, cm; x – distance from release source, m.
Functions )(xg and ),( 0 xzf are estimated
depending of atmosphere stability category due to the
following formulae:
)1()( 21 21
bb xaxaxg += , (9)
[ ]
[ ]
≤+
>+
=
сm.10z1
сm;10z1
021
021
0
21
21
,)xc(xcln
,,)xc(xcln
)x,z(f
dd
dd
(10)
The main factors needed for estimates are shown in
Tables 3-5.
Table 3. Factors applicable for estimates of jet lateral
dispersion yσ and function )(xg
Atmospher
e stability
category by
Pasquill
,max
zσ
m
a1 b1 а2 b2
А 1600 0,112 1,06 5,38·10-4 0,815
B 920 0,130 0,950 6,52·10-4 0,750
C 640 0,112 0,920 9,05·10-4 0,718
D 400 0,098 0,889 1,35·10-3 0,688
E 220 0,0609 0,895 1,96·10-3 0,684
F 100 0,0638 0,783 1,36·10-3 0,672
Table 4. Factors of function ),( 0 xzf modifying zσ
for diverse roughness height 0z
Roughness
height 0z , cm c1 d1 c2 d2
1 1,56 0,0480 6,25·10-4 0,45
4 2,02 0,0269 7,76·10-4 0,37
10 2,73 0 0 0
40 5,16 -0,098 5,38·10-2 0,225
100 7,37 -0,00957 2,33·10-4 0,6
400 11,7 -0,128 2,18·10-5 0,78
Table 5. Roughness height 0z for diverse types of
surface microrelief
Microrelief 0z , cm
Snow, 1 cm high lawn 0,1
Mown and low grass to 15 cm 0,6…2
High grass to 6 cm 4…9
Heterogenous surface with
alternate grass areas, shrubs etc. 10…20
Park, forest to 10 m height 20…100
4. RELEASES OF RADIOACTIVE AEROSOL
ADMIXTURES INTO ATMOSPHERE
According to [1], individual average annual dose
rate is conditioned by intake of radioactive substances in
human organism with foodstuff, is defined as follows:
FDs KAH ⋅=
••
, (11)
where – individual average annual dose rate, Sv/s;
•
sA –
contamination intensity, Bq/(m2⋅c).
igFIFD BKK ⋅= , (12)
97
where FIK – factor linking contamination level with
radionuclide intake into organism, m2; igB – factor
linking activity coming with foodstuff with effective
dose (depends on age) [3], Sv/Bq.
Effective dose rate of external exposure vH (Sv/s)
due to each nuclide for a man staying on earth surface
conditioned by a radioactive aerosol cloud, which was
produced as result of release, is defined from the
formula:
ayVv BAH ~⋅= , (13)
where AV – radionuclide volumetric activity, Bq/m3;
γaB~ – transient dosimetric multiplier (depending on
age) characterizing effective dose rate created by a
radioactive aerosol cloud of single concentration at open
earth surface [3], Sv m3/(s⋅Bq).
Effective dose intH (Sv) conditioned by inhalation
intake of radioactive aerosol, is estimated by the
formula:
Vageageint ATeVH τ= , (14)
where ageV – breathing rate (depends on age) [4],
m3/hour; T – stay time in aerosol cloud, hour; ageeτ –
dose per unit of activity intake by inhalation way
(depends on age) [3], Sv/Bq.
Effective dose rintH _ (Sv) conditioned by
inhalation intake of resuspended dust is estimated by the
formula:
*_ Vagerint AVTeH τ= , (15)
where *VA – volumetric activity due to resuspended
dust, Bq/m3.
Ratio of volumetric activity produced due to
resuspended dust and nuclide volumetric activity under
absence of wind rise, is defined as follows:
λ
+
λ+λ
Λ+= αα
2
2
21
1
max )(* KK
H
v
A
A
Z
g
V
V , (16)
where 15
1 m10 −−
α =K ; 19
2 m10 −−
α =K ; 1λ –
constant of deflation factor reduction for rapid phase,
17
1 c1046,1 −−⋅=λ ; 2λ – constant of its more prolonged
reduction, 110
2 s102,2 −−⋅=λ ; max
ZH – mixing layer
height, m, which is defined by formula:
maxmax )2/( zZH σ⋅π= . (17)
Dose conditioned by radiation of soil contaminated
surface, is defined from the formula:
effSssurf BAH τ= γ
••
, (18)
where
•
surfH – expectable dose, Sv/s; effSB τγ –
expectable dose per contamination unit (depends on
age), Sv m2/Bq.
Considering the fact that main contribution into
external exposure from soil contaminated surface
induces 137Cs, 71001,1 −
γ ⋅=τ effSB Sv m2/Bq [1].
5. PROCEDURE FOR ADMISSIBLE
RELEASE ESTIMATE
To estimate admissible release, PRC-1 program was
created, which allows estimating AR with considering
all described ways of dose formation from NSC
releases. The program features permit working with all
initial data, changing them with the help of MS Excel,
as well as displaying any needed information in graphic,
or table form.
For more pictorial view and facilitation of work with
the software, it was compiled as follows. First, single
release impact to public is estimated, thereafter by way
of iterations with indicated accuracy the set of releases
is made to achieve required dose quote.
In estimating AR, radionuclide content of NSC
release is considered. Based on the fact that projected
NSC existing time – 100 years, radionuclide content of
releases through each 10 years of NSC operation was
estimated as an assumption that radionuclide content
correspond to SO fuel content [2] in the same year.
6. ADMISSIBLE RELEASE VALUES
Based on above procedure, estimate of admissible
release for total NSC operational life time for critical
group of public was made. Besides, an estimate of
admissible release for β- and α-emitting nuclides and
dust fuel release from the NSC was made. Estimate
results are shown in Table 6. Estimates were made for
five reference ages of man (new-born, 1 year, 5 years,
10 years, 15 years, adult), and for the two sexes.
Reduction with time of summary AR and β-emitting
radionuclide AR is conditioned by influence of different
chains of radioactive decay. Simultaneously, the main
β-emitting radionuclides decay with half-life being 30
years and less. At the same time, total alpha-activity
even increases due to 241Am accumulation resulted by
241Pu β-decay (maximum value will be reached
approximately to the year of 2050). Because of it,
contribution to dose from α-emitting radionuclides will
increase, and their AR will grow. Naturally, total
amount of dust fuel will also increase, whose release
will lead to dose for public of 40 µSv/year at 10 km
zone border.
Contributions to quote due to diverse dose
formation ways in the beginning (for 2010 year) and in
the end of NSC operation (2110 year) are submitted in
Tables 7 and 8.
In the beginning of NSC operation (Table 7), dose
will be, mainly, defined by internal exposure (around 34
µSv/year), in addition due to radionuclide intake
through food chains (around 28 µSv/year).
Under external exposure, dose due to immersion in
cloud is negligible one and relatively low dose (1,1 µ
Sv/year) is mainly defined by 137Cs radiation from
contaminated ground surface.
In estimating doses under inhalation intake of
radionuclides, two mechanisms were considered too –
direct exposure in radioactive cloud due to exposure
release occurred and from resuspension of dust
precipitated on surface. Beginning from, approximately,
the third year of operation, relative contribution to
inhalation intake dose directly from a cloud remains,
practically, constant one, and makes around 2/3 of all
inhalation doses.
Ingest dose is, mainly, defined by dose conditioned
by aerial way of contamination of agricultural produce
(around 24 µSv/year). There are less, at a significant
rate, of doses (2,2 µSv/year) due to contamination of
water medium resulted by releases. Around 5,4 µ
Sv/year – dose due to root way of contamination.
To NSC operation end, the situation can somehow
change (Table 8). Determining contribution to dose will
induce ingestion intake of alpha-emitting nuclides. Dose
due to that mechanism may total around 28 µSv/year,
some 6 µSv/year will be defined by intake through food
chains, mainly, due to alpha-emitting nuclides.
One should consider that the releases from NSC
operation will not be uniform in the course of a year,
and will depend on type and intensity of works being
implemented. In case of conduct of dust-producing
works in pre-harvest period, which will be accompanied
by intensive release during a short time period, annual
dose can essentially increase. That fact should be
considered when planning the works in NSC.
The main conclusions of carried out modeling are:
• before 2080, critical group is 15 year teenagers of
male sex, after 2080 – adults of male sex;
• during all NSC operation period is expected that
most ingestion dose will be from bread
consumption;
• in NSC operation start, ingestion dose is mainly
defined by dose conditioned by aerial way of
contamination of agricultural produce;
• in NSC operation end, determining contribution to
dose will be induced by inhalation intake of alpha-
emitting nuclides.
Table 6. Main results of admissible release estimate
Year Radionuclide mix
AR, Ci
Radionuclide mix
AR, Bq
Beta-emitting
radionuclide
AR, Ci
Beta-emitting
radionuclide
AR, Bq
Alpha-emitting
radionuclide
AR, Ci
Alpha-emitting
radionuclide
AR, Ci
Fuel dust
AR, g
2010 8,3 3,07E+11 8,1101 3,00E+11 0,1899 7,03E+09 167,71
2020 7,6 2,81E+11 7,3581 2,72E+11 0,2419 8,95E+09 200,52
2030 7 2,59E+11 6,7033 2,48E+11 0,2967 1,10E+10 238,77
2040 6,4 2,37E+11 6,0485 2,24E+11 0,3515 1,30E+10 279,75
2050 5,85 2,16E+11 5,4415 2,01E+11 0,4085 1,51E+10 325,06
2060 5,3 1,96E+11 4,8359 1,79E+11 0,4641 1,72E+10 371,54
2070 4,8 1,78E+11 4,2789 1,58E+11 0,5211 1,93E+10 421,36
2080 4,35 1,61E+11 3,7702 1,39E+11 0,5798 2,15E+10 474,57
2090 3,9 1,44E+11 3,2676 1,21E+11 0,6324 2,34E+10 524,61
2100 3,4 1,26E+11 2,7354 1,01E+11 0,6646 2,46E+10 559,17
2110 2,95 1,09E+11 2,2613 8,37E+10 0,6887 2,55E+10 587,79
Table 7. Contribution into effective dose from admissible release of diverse nuclides and diverse ways of impact at
NSC operation start
Dose due to intake
through vegetative
and meat chains for
individual
radionuclides,
µSv
Internal exposure External exposure
Dose due to intake through alimentary chains, µSv
Contamination
aerial way
Contamination
root way
Dose due to
consumption of
fish and water, µ
Sv
Dose due to
RS
inhalation, µ
Sv
Dose due to
immersion in cloud,
µSv
External dose from
surface
contamination
137Cs, µSv
137Cs 9,26
90Sr 16,14
Alpha-emitting
nuclides 2,28
241Pu 0,36
24,34 3,65 5,4
0,08 2,05E-07
0,13 1,81E-07 1.1
5,3 4,13E-08
1,85E-03 2,25E-11
Sum 28,04 33,39 5,51
Dose sum of internal exposure 38,9
Dose sum of
external exposure 1,1
99
Table 8. Contribution into effective dose from admissible release of diverse nuclides and different impact ways at
NSC operation end
Dose due to intake
through vegetative
and meat chains for
individual
radionuclides,
µSv
Internal exposure External exposure
Dose due to intake through alimentary chains, µSv
Contamination
aerial way
Contamination root
way
Dose due to
consumption of
fish and water, µ
Sv
Dose due to RS
inhalation,
µSv
Dose due to
immersion in
cloud,
µSv
External dose from
surface
contamination 137Cs,
µSv
137Cs 1,19
90Sr 3,35
Alpha-
emitting
nuclides
27,56
241Pu 0,04
31,03 1,10 2,21
6,79E-03 8,66E-08
2,00E-02 6,74E-08
0,5
5,14E+00 1,74E-07
1,35E-04 2,30E-12
Sum 32,13 34,34 5,17E+00
Dose sum of internal exposure 39,5
Dose sum of
external
exposure
0,5
Thus, when planning activities for protection of
public and environment during NSC operation, radiation
monitoring must be provided of NSC releases, of
radionuclide concentrations in air (in first turn of 90Sr,
137Cs and 241Am), of surface contamination levels, of
radionuclide content in foodstuff.
It seems as inexpedient to grow cereals (except feed-
preparing works), near exclusion zone borders,
especially in case of reduction of its dimensions.
Besides, one should consider the fact that in case of
reduction of borders of 30 km exclusion zone to 10 km,
practical implementation of all agricultural works must
be provided on the basis of recommendations for
agricultural activities on the territories that are
contaminated with radionuclides. It implies that a
complex of measures (counter-measures) should be
implemented to minimize radionuclide intake into the
products of agricultural industry and conduct of
continuous radioecological monitoring.
REFERENCES
1. N.G. Gusev, V.A. Belyaiev. Radioactive releases in
atmosphere, reference book. M.:
“Energoatomizdat”, 1986, p. 32, 91, 95-130 (in
Russian).
2. The “Shelter's” current safety analysis and situation
development forecast. (Updated version). Kiev:
TACIS, 1998, p. 77.
3. U.S. Environmental Protection Agency, Federal
Guidance. Report 13 Cancer Risk Coefficients for
Environmental Exposure to Radionuclides: CD
Supplement, EPA 402-C-99-001, Rev. 1. Oak Ridge
National Laboratory, Oak Ridge, TN; U.S.
Environmental Protection Agency, Washington, DC.
4. Norms of radiation safety of Ukraine (NRBU-97).
State hygienic standards. GGN 6.6.1.-6.5.001-98.
Official edition. Kiev, 1998, p. 74.
МАТЕМАТИЧЕСКОЕ МОДЕЛИРОВАНИЕ ВОЗДЕЙСТВИЙ ПРИ ВЫБРОСАХ ИЗ ОБЪЕКТА
“УКРЫТИЕ”
В.Г. Батий, С.А. Паскевич, В.М. Рудько, А.А. Сизов, В.Н. Щербин
Описана методика математического моделирования воздействий на население по всем возможным путям
в результате возможного выброса радиоактивных веществ. Приведены результаты расчета допустимых
выбросов на различных этапах эксплуатации нового безопасного конфайнмента над существующим
объектом “Укрытие” Чернобыльской АЭС.
МАТЕМАТИЧНЕ МОДЕЛЮВАННЯ ВПЛИВІВ ПРИ ВИКИДАХ З ОБ’ЄКТУ “УКРИТТЯ”
В.Г. Батій, С.А. Паскевич, В.М. Рудько, А.О. Сізов, В.М. Щєрбін
Описано методику математичного моделювання впливів на населення за всіма можливими шляхами у
результаті можливого викиду радіоактивних речовин. Надано результати розрахунку допустимих викидів на
різних етапах експлуатації нового безпечного конфайнменту над існуючим об’єктом “Укриття”
Чорнобильської АЕС.
2. PROCEDURE FOR RELEASE IMPACT ESTIMATE
3. RADIOACTIVE SUBSTANCE CONCENTRATIONS IN THE AIR AND SOIL.
CONTINUOUS RELEASES
4. RELEASES OF RADIOACTIVE AEROSOL ADMIXTURES INTO ATMOSPHERE
5. PROCEDURE FOR ADMISSIBLE RELEASE ESTIMATE
6. ADMISSIBLE RELEASE VALUES
REFERENCES
|
| id | nasplib_isofts_kiev_ua-123456789-80556 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T17:20:19Z |
| publishDate | 2004 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Batiy, V.G. Paskevich, S.A. Rudko, V.M. Sizov, A.A. Shcherbin, V.N. 2015-04-18T20:27:47Z 2015-04-18T20:27:47Z 2004 Mathematical simulation of “Shelter” object releases impacts / V.G. Batiy, S.A. Paskevich, V.M. Rudko, A.A. Sizov, V.N. Shcherbin // Вопросы атомной науки и техники. — 2004. — № 5. — С. 96-100. — Бібліогр.: 4 назв. — англ. 1562-6016 PACS: 28.41Te https://nasplib.isofts.kiev.ua/handle/123456789/80556 Methods of mathematical modeling of radiological human impacts are described. Calculation of admissible
 releases at different exploitation stages of New Safe Confinement at the existing ChNPP “Shelter” object are given. Описано методику математичного моделювання впливів на населення за всіма можливими шляхами у
 результаті можливого викиду радіоактивних речовин. Надано результати розрахунку допустимих викидів на
 різних етапах експлуатації нового безпечного конфайнменту над існуючим об’єктом “Укриття”
 Чорнобильської АЕС. Описана методика математического моделирования воздействий на население по всем возможным путям
 в результате возможного выброса радиоактивных веществ. Приведены результаты расчета допустимых
 выбросов на различных этапах эксплуатации нового безопасного конфайнмента над существующим
 объектом “Укрытие” Чернобыльской АЭС. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Применение ядерных методов Mathematical simulation of “Shelter” object releases impacts Математичне моделювання впливів при викидах з об’єкту “Укриття” Математическое моделирование воздействий при выбросах из объекта “Укрытие” Article published earlier |
| spellingShingle | Mathematical simulation of “Shelter” object releases impacts Batiy, V.G. Paskevich, S.A. Rudko, V.M. Sizov, A.A. Shcherbin, V.N. Применение ядерных методов |
| title | Mathematical simulation of “Shelter” object releases impacts |
| title_alt | Математичне моделювання впливів при викидах з об’єкту “Укриття” Математическое моделирование воздействий при выбросах из объекта “Укрытие” |
| title_full | Mathematical simulation of “Shelter” object releases impacts |
| title_fullStr | Mathematical simulation of “Shelter” object releases impacts |
| title_full_unstemmed | Mathematical simulation of “Shelter” object releases impacts |
| title_short | Mathematical simulation of “Shelter” object releases impacts |
| title_sort | mathematical simulation of “shelter” object releases impacts |
| topic | Применение ядерных методов |
| topic_facet | Применение ядерных методов |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/80556 |
| work_keys_str_mv | AT batiyvg mathematicalsimulationofshelterobjectreleasesimpacts AT paskevichsa mathematicalsimulationofshelterobjectreleasesimpacts AT rudkovm mathematicalsimulationofshelterobjectreleasesimpacts AT sizovaa mathematicalsimulationofshelterobjectreleasesimpacts AT shcherbinvn mathematicalsimulationofshelterobjectreleasesimpacts AT batiyvg matematičnemodelûvannâvplivívprivikidahzobêktuukrittâ AT paskevichsa matematičnemodelûvannâvplivívprivikidahzobêktuukrittâ AT rudkovm matematičnemodelûvannâvplivívprivikidahzobêktuukrittâ AT sizovaa matematičnemodelûvannâvplivívprivikidahzobêktuukrittâ AT shcherbinvn matematičnemodelûvannâvplivívprivikidahzobêktuukrittâ AT batiyvg matematičeskoemodelirovanievozdeistviiprivybrosahizobʺektaukrytie AT paskevichsa matematičeskoemodelirovanievozdeistviiprivybrosahizobʺektaukrytie AT rudkovm matematičeskoemodelirovanievozdeistviiprivybrosahizobʺektaukrytie AT sizovaa matematičeskoemodelirovanievozdeistviiprivybrosahizobʺektaukrytie AT shcherbinvn matematičeskoemodelirovanievozdeistviiprivybrosahizobʺektaukrytie |