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Nuclear Science and Technology, Vol.4, No. 4 (2014), pp. 09-16
Assessment of radiation dose caused by radioactivegaseous
effluent released from nuclear power plant Ninh Thuan 1
under scenario of normal operation
Do Xuan Anh, Le Dinh Cuong, Duong Duc Thang, Vuong Thu Bac, Nguyen Thi Thu Ha,
Nguyen Quang Long, Trinh Van Giap, Nguyen Hao Quang*, Nguyen Tuan Khai
Institute for Nuclear Science and Technology (INST), 179 Hoang Quoc Viet, Hanoi
*
Vietnam Atomic Energy Institute (VINATOM), 59 Ly Thuong Kiet, Hanoi
(Received 15 December 2014, accepted 23 January 2015)
Abstract: Based on guides RG 1.109, RG 1.111 published by United States Nuclear Regulatory
Commission (USNRC) our research concentratesinassessing radiation doses caused by radioactive
substances released from the nuclear power plant (NPP) Ninh Thuan 1 under the scenario of normal
operation using software package NRCDose72 provided by the USNRC. The database including the
released radioactive nuclides, meteorology, terrain, population and agricultural production
activities have beencollectedand processed to build the input data for the model calculation. The wind
rose distribution obtained from the meteorological data in a five-year period from 2009-2013 showed
that the radioactive nuclides released to environment spread in two main wind directions which are
North East and South West. The
XJQ
(s/rrr') and
DIQ
(s/rrr') qualities which are, respectively, the ratio
of activity concentration to release rateand that of deposition density of radioactive nuclides to release
rate were calculated within an area of 80 km radius from the NPP site using XOQDOQ. Population
doses were calculated using GASP AR. The XOQDOQ and GASP AR are two specific softwares in
NRCDose72 package.
Keywords: NPP, radioactive release, radiation dose, population dose,.xJQ and DIQ
I. INTRODUCTION
Currently, Vietnam is actively preparing
infrastructure forthe first two nuclear power
plant (NPP) projects Ninh Thuan 1&2 which is
planned to build with a total capacity of 2,000
MW
for each. When going into operation, the
NPP will.release radioactive nuclides into the
atmosphere. The radioactive effluent
undergoing dispersion in air and deposition on
ground will cause impact to the environment
and human. Therefore, research for transport
and dispersion of radioactive substances in
atmosphere, and assessment for radiation dose
to the public are of essential requirement for an
NPP project. In addition, the calculation results
will provide the necessary data for the
Environmental Impact Assessment (EIA) and
support for regulatory organization m
reviewing the Safety Analysis Report (SAR).
Radioactive releases from vanous
nuclear facilities, in general, may contribute to
radiation exposure through two main
pathways: (1) External exposures by direct
radiation from radioactive plumes or from
radioactive nuclides deposited on the ground,
and (2) Internal exposure due to inhalation and
ingestion of radioactive substances. The
magnitude of exposure is dependent on
atmospheric dispersion and deposition
processes.
In this work we focused on investigating
the radioactive release from the NPP Ninh
Thuan 1 and assessing radiation dosesfor the
populationunder the scenario of normal
©2014 Vietnam Atomic Energy Society and Vietnam Atomic Energy Institute
ASSESSMENT OF RADIA nON DOSE CAUSED BY RADIOACnVEGASEOUS EFFLUENT ...
operationusing software package
NRCDose72.To build the data input for the
model calculation the database on
meteorology, terrain, population and
agricultural production activities has been
collected and processed within a radius scope
of 80 km from the NPP site, where the wind
rose distributionwas obtained from processing
the meteorological data in a five-year period of
2009-2013. The released nuclear data
IS
referred from the United Nations Scientific
Committee on the Effects of Atomic Radiation
(UNSCEAR), in which the annual normalized
release in Bq/(GWe-year) for the radioactive
isotopes has been published for the popular
reactor types such as PWR, BWR, FBR and
some others based on the average evaluation
on a period from 1990-1997 [1,2]. Our
assessments have been performed using the
released data for PWR type with an assumed
total power of 2000 MW
e.
The ratio of activity
concentrations
XJQ
(s/rrr') and that of
radioactive deposition densities
D/Q
(s/rn")
were calculated using XOQDOQ, in which it is
assumed that the radioactive substance is
dispersed by the Gaussian model. The obtained
results on
XJQ
and
D/Q
values were used for
evaluating the population doses using
GASP AR. As mentioned above, the XOQDOQ
and GASP AR are two softwares In
NRCDose72 package [3,4],
n. COMPUTER CODE DESCRIPTION
A.XOQDOQ
Computation program XOQDOQ is used
In the independent meteorological evaluation
of routine or anticipated, intermittent releases
of radioactive nuclides at commercial nuclear
power plants. It is primarily designed to
calculate annual relative effluent
concentrations,
X/Q
values, and annual
average relative deposition,
D/Q
values, at
locations specified by the user, and at various
standard radial distances and segments for
downwind sectors. Evaluations of anticipated
intermittent (e.g. containment or purge)
releases which occur during routine operation
may also be evaluated using the program.
Evaluation of intermittent releases provides
both
XJQ
and
D/Q
values at various standard
locations, as well as user-inputted specific
points of interest.
The input of the program includes
meteorological and topographic data.
Meteorological data is as a joint frequency
table, i.e. a table of the fractional occurrence
during a given time period of a particular
combination of stability class type, wind
direction, and wind speed class. The wind
direction
IS
classified into 16 sectors
proceeding clockwise from N through NNW.
The wind speeds are grouped into classes, with
the program allowing up to 14 separate classes,
which include a class for calm wind speeds.
Atmospheric stability is grouped according to
seven categories from extremely unstable to
extremely stable. Terrain elevation (in meters,
compared to the factory floor) is the maximum
height in the topographic data collected in the
80 km radius from the NPP site. The direction
and distance from the source are included in
terrain elevation data.
In this work the meteorological data at
Ninh Thuan including wind direction, wind
speed and atmospheric stability has been
collected and processed based on a five-year
database provided by Phan Rang
meteorological stationand the National
Oceanic and Atmospheric Administration of
United States (NOAA). The terrain data is
built using the topographic map within the 80
km radius around the site planned for NPP
Ninh Thuan 1.
10
1
followi
x ( .
-xK
Q
1
X
I!:'?
I,)
X
exp
\
concen
distanc
the
do'
wind-s]
stabilit
U;is
n
class;
I
stabilit
probab
class, .
directir
(in mel
to radi
wind-s
factor I
the ith
Kth
v
correct
stagna:
wind-d
deposit
relatior
deposi
distant
relativ
class ::
DO XUAN ANH et a!.
'U ...
:tvarious
ients
for
iticipated
purge)
operation
program.
provides
standard
specific
The values X/Q is determined by the
following formula [3]:
~(x, K)
=
Z.~2
X
RF(x, K)
",N,7
DEPLij (x,K)DECi
(:t;)fij
(K)
X£.. . _----"'-- __
--0-_"'--_
I,)
u,
(x)azjCx)
x
exp -
0.5 ( ~: )
O"Zj(x)
(1)
includes
data.
'equency
currence
articular
~, wind
le wind
sectors
INNW.
;es,with
classes,
speeds.
rding to
table to
where ~
(x,
K)
is average effluent
Q
concentration normalized by source strength at
distance xin directional sector
K
(s/nr'); xis
the downwind distance (meters); iis the ith
wind-speed class; jis the /h atmospheric
stability class; Kis the
k"
wind-direction class;
U;is
mid-point value of the itb wind-speed
class;
rYz/x)
is the vertical plume spread for
stability class j at distance x; /y(K) is the joint
probability of occurrence of the ilh wind-speed
class, /h is stability class, and Kth is wind
direction sector;
he
is the effective plume height
(in meters); DEC;{x)is the reduction factor due
to radioactive decay at distance x for the ith
wind-speed class; DEPL(x,K) is the reduction
factor due to plume depletion at distance
x
for
the ithwind-speed class, jth stability class and
Kth wind-direction class; RF(x,K)is the
correction factor for recirculation and
stagnation at downwind distance xand Kth
wind-direction class.
meters,
aximum
d in the
lirection
uded in
data at
I,
wind
s been
ve-year
Rang
ational
tion of
data is
the 80
Ir
NPP
For each directional sector, relative
deposition is computed by the following
relationshipfor a specific downwind distance [3]:
~ ( ). _ RP (x.K)
L~t
DU
fij
(K)
Q
X,K - (::~
(2)
where ~
(x,
K) is the average relative
Q
deposition per unit area at a downwind
distance xand direction
K,
in meter"; Dijis the
relative deposition rate for the itb wind-speed
class and the /h stability class;/y(K) is the joint
probability of occurrence of the ilh wind-speed
class; RF(x,K) is the correction factor for
recirculation and stagnation at downwind
distance xand Kthwind-direction class.
B.GASPAR
GASP AR is a computer code used by
the USNRC in radiation dose assessment for
individuals and groups of people contaminated
by the release of radioactive nuclides into the
air environment of nuclear power plants in
normal operation conditions. The theoretical
basis for the radiation dose calculations of the
code is based on Regulatory Guide 1.109 and
NUREG/CR-4653 [5,6]. Data input of the
program includes:
(1) Population: Data on the total
population and population distribution for four
distinct age groups: infant, child, teenager and
adultin each sector (subregion);
(2) Crop and cattle breeding: Data on
production and distributions of meat, milk and
production.
These two data sets have been processed
within the 80 kmradius around the NPP site.
(3) Radioactive release: Data on the
activity (Ci) oftheradioactive nuclides released
to the environment and the rate of the
radioactive waste (Ci/year);
(4) Meteorology:
Data on atmospheric dispersion
parameters (sec/m:') for use in population dose
calculations for the undecayed/undepleted
dispersion and the decayed/undepleted
dispersion;
Data onatmospheric dispersion
parameters (sec/m') with decay and depletion
for use in population dose calculations for the
decayedldepleteddispersion;
- Data on ground deposition parameter
(mvyear) for use inpopulation dose
calculations;
11
ASSESSME T Of RADIATIO DOSE CAUSED BY RADIOACTIVEGASEOUS EffLUE T ...
It should be noted that the
meteorological data can be imported either
directly into the software or from the output of
XOQDOQ software.
The outputs of GASP AR include:
- Gamma air and beta air dose;
- Annual effective dose from all other
noble gas releases;
- Skin dose;
- Annual organ dose from external
irradiation by deposited radioactive nuclides;
- Annual organ dose from inhalation;
- Annual organ dose from ingestion of
radioactive nuclides in food;
- Annual population integrateddose.
Ill. RESULTS D DISCUSSION
A. Meteorological data processing
Fig. 1: The wind rose distribution obtained from the
database of the Phan Rang station
Based on the database provided by the
Phan Rang station in the five-year period from
2009 to 2013 the meteorological data was
processed to obtainthe wind rose distribution as
shown in figure 1 for the wind direction and
speed in the area planned for construction of
the NPP Ninh Thuan 1.We can see that the
wind direction and intensity IS mainly
concentrated in two directions which are the
North East and South West. These are the two
main wind directions passing through the
provinces of the region in the South Central
Coast and Tay Nguyen.
At present it is impossible to determine
the atmospheric stability from the Phan Rang
station's database due to the lack of some
necessary measurements such as the
atmospheric temperature as a function of
height. We are discussing on a possibility to
evaluate this parameter based on the cloud
observation data. In this work the atmospheric
stability was evaluated using the
meteorological database down loaded from the
National Oceanic and Atmospheric
Administration (NOAA) of the United States.
B. Gaseous effluent distribution
The output from the program XOQDOQ
was designed to present the maximum amount
of information on each release point, including:
- XlQ values (s/rrr') at 22 specific
distances ranging from 0.80 to 80 kmfrom the
site;
- X/Q values for 10 distance intervals;
- D/Q values (s/rrr') at 22 specific
distances ranging from 0.80 to 80 km from the
site;
- D/Q values for 10 distance intervals;
- XlQ and D/Q values at specific points
of interest.
The obtained calculation results made us
possible to build the XlQ-value and D/Q-value
distributions as a function of distance ranging
from 0.8 to 80 km from the NPP site as shown in
figure 2. We can see clearly that the XlQ and
D/Q values are dominant in two directions of
North East and South West. This is consistent
withthe obtained wind rose distribution, where
the wind frequencies are also high in these two
directions (as shown in figure 1).
12
12
11.8
116
Cl
~
j
11.4
11.2
11
10.8
C. Pop
gives
t
popula
Pathw
Plum
Grow
Inbalat
Vegetz
Cowrr
Me,
Tot:
ENT ...
.ch are the
srethe two
trough the
ith
Central
determine
PhanRang
, of some
as the
mction of
ssibility to
the cloud
tmospheric
ing the
:I
from the
tmospheric
:dStates.
XOQDOQ
un
amount
including:
2
specific
mfrom the
tervals;
2 specific
n from the
tervals;
ific points
s made us
D/Q-value
ce ranging
s shown in
: XlQ
and
rectionsof
consistent
ion,where
thesetwo
DO XUAN ANH et a1.
12
11.8
11.6
11.4
112
11
10.8
108.4 1086 108.8 109 109.2 1094 1096
Longitude
1084 108.6 1088 109 1092
Longitude
1094 1096
Fig.2. Distribution on
XJQ
values (left) and
D/Q
values (right)
Within 80 km radius from the NPP site.
C. Population dose assessment
The output of the program GASP AR
gives the calculation results forthe annual total
population dose and annual individual dose for
three distinct age groups including child,
teenager and adult at the locations of interest.
The details are given in Tables I-Ill.
Table I: Calculation results for the annual total population dosein 80 km radius
Pathway Annual total population dose (mSv)
Effective Gi-lli Bone Liver Kidney Thyroid Lung Skin
Plume 2.30E-02 2.30E-02 2.30E-02 2.30E-02 2.30E-02 2.30E-02 2.55E-02 2.21E-Ol
2.12% 2.11% 2.15% 2.14% 2.15% 1.71% 2.39% 13.30%
Ground 9.97E-Ol 9.97E-Ol 9.97E-Ol 9.97E-Ol 9.97E-Ol 9.97E-Ol 9.97E-Ol 1.41E+00
92.09% 91.58% 93.57% 92.95% 93.50% 74.23% 93.16% 84.61%
Inhalation 2.31E-02 2.20E-02 2.20E-02 2.22E-02 2.20E-02 3.64E-02 2.51E-02 2.18E-02
2.13% 2.02% 2.07% 2.07% 2.06% 2.71% 2.34% 1.31%
Vegetable 1.83E-02 2.76E-02 1.63E-02 2.01E-02 1.67E-02 2.62E-02 1.57E-02 1.02E-02
1.69% 2.54% 1.53% 1.87% 1.56% 1.95% 1.47% 0.61%
Cowmilk 1.06E-02 1.81E-03 1.30E-03 1.36E-03 1.27E-03 1.91E-O1 1.24E-03 5.26E-04
0.98% 0.17% 0.12% 0.13% 0.12% 14.22% 0.12% 0.03%
Meat 1.07E-02 1.74E-02 5.98E-03 9.02E-03 6.39E-03 6.95E-02 5.63E-03 2.41 E-03
0.99% 1.59% 0.56% 0.84% 0.60% 5.17% 0.53% 0.14%
Total 1.08E+00 1.09E+00 1.07E+00 1.07E+00 1.07E+00 1.34E+00 1.07E+00 1.66E+00
13
ASSESSMENT OF RADIATION DOSE CAUSED BY RADIOACTIVEGASEOUS EFFLUE T ...
Table 11: Calculation results for the annual total population dose induced by the released radio-nuclides
Radioactive Annual total population dose (mSv)
nuclide Effective Gi-lli Bone Liver Kidney Thyroid Lung Skin
jH 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E-02
3.23% 3.21% 3.28% 3.26% 3.27% 2.60% 3.26% 2.10%
5~CO 2.38E-02 2.85E-02 2.29E-02 2.34E-02 2.30E-02 2.28E-02 2.31E-02 2.77E-02
2.19% 2.62% 2.15% 2.18% 2.16% 1.70% 2.16% 1.66%
oUCo 8.69E-Ol 8.82E-Ol 8.66E-Ol 8.73E-Ol 8.67E-Ol 8.66E-Ol 8.68E-Ol 1.03E+OO
80.24% 81.03% 8l.27% 8l.36% 8l.29% 64.44% 8l.l2% 62.15%
~)Kr 8.46E-05 8.46E-05 8.46E-05 8.46E-05 8.46E-05 8.46E-05 1.98E-04 9.36E-03
-0% -0% -0% -0% -0% -0% 0.02% 0.56%
u'I 1.49E-02 1.27E-03 1.23E-03 1.19E-03 1.19E-03 2.80E-Ol 1.22E-03 2.06E-03
l.37% 0.12% 0.11% 0.11% 0.11% 20.81% 0.11% 0.12%
UjXe 1.65E-02 l.65E-02 1.65E-02 1.65E-02 1.65E-02 1.65E-02 1.87E-02 l.65E-01
1.52% 1.51% 1.55% 1.54% l.55% l.23% 1.75% 9.92%
135Xe 6.38E-03 6.38E-03 6.38E-03 6.38E-03 6.38E-03 6.38E-03 6.62E-03 4.69E-02
0.59% 0.59% 0.60% 0.59% 0.60% 0.47% 0.62% 2.82%
u"Cs 1.95E-02 1.98E-02 1.95E-02 1.95E-02 l.95E-02 l.94E-02 1.93E-02 2.65E-02
1.80% l.81% 1.83% l.82% 1.83% 1.45% 1.81% 1.59%
IJICs
9.80E-02 9.91E-02 9.82E-02 9.80E-02 9.80E-02 9.80E-02 9.80E-02 3.18E-01
9.05% 9.10% 9.21% 9.13% 9.19% 7.30% 9.15% 19.08%
Total 1.08E+00 1.09E+00 1.07E+00 1.07E+00 1.07E+00 1.34E+00 1.07E+00 1.66E+OO
Table
Ill:
Calculation results for theannual total effective dose to individual for three age groups:
child, teenager and adult at the locations of interest.
Distance Annual total effective dose to individual for
Location Direction (km) age groups (mSv) for age groups
Adult Teenager Child
VinhTuong ( Thuan Nam ) N 1.165 1.46E-04 1.93E-04 3.15E-04
Son Hai (Thuan Nam) S 2.18 3.15E-05 4.16E-05 6.77E-05
TuThien (Thuan Nam) N 3.38 2.36E-05 3.12E-05 5.07E-05
BauNgu ( Thuan Nam ) NW 5.9 6.01E-06 7.92E-06 1.29E-05
HoaThuy ( NinhPhuoc ) NNW 9.1 3.45E-06 4.54E-06 7.34E-06
Phuoc Lap ( Thuan Nam ) NW 11.25 1.96E-06 2.57E-06 4.15E-06
Quan The ( Thuan Nam ) W 12.5 2.47E-06 3.24E-06 5.23E-06
HieuThien ( Thuan Nam ) WNW 13.45 1.61E-06 2.12E-06 3.42E-06
Thuong Diem ( Thuan Nam ) SW 15.48 1.58E-05 2.09E-05 3.41E-05
14
Lac Tien (
Ca Na (TI
Phan Rang
Lien Huon
Cho Lau (
Thanh My
To Hap (}
Cam Ranh
Lien Nghi:
We
dose
evr
radioactiv
1
are mue
mSv guid
Thl
10
Table
tendency
at Lien N
the~
value is a
Vinh Tuo
Frc
shown in
-F
ground
contributi
for bone,
- F
60Co indu
62 to 81~
This is cc
normal
0
isconsidei
radioactix
induced a
materials
corrosion
contributi
JT ...
-nuclides
Skin
12 3.49E-02
2.10%
22.77E-02
1.66%
11.03E+00
)
62.1S%
49.36E-03
0.S6%
3
2.06E-03
0.12%
2
1.6SE-Ol
9.92%
3
4.69E-02
2.S2%
2
2.6SE-02
~
I.S9%
2
3.1SE-01
~
19.0S%
0
1.66E+00
ps:
vidualfor
Child
11SE-04
6.77E-OS
S.07E-OS
l.29E-OS
7.34E-06
4.lSE-06
S.23E-06
142E-06
3.41E-OS
DO XUAN ANH et al.
LacTien (Thuan Nam) WSW 14.42 3.6SE-06 4.S0E-06 7.78E-06
CaNa ( Thuan Nam ) SW 16.79 l.3SE-OS l.S3E-OS 2.99E-OS
PhanRang - Thap Cham N 14.2 1.9SE-06 2.S9E-06 4.18E-06
LienHuong ( TuyPhong ) SW 38.7S 3.34E-06 4.4IE-06 7.19E-06
ChoLau (BacBinh) WSW 60.9 3.ISE-07 4.09E-07 6.S3E-07
ThanhMy (Don Duong) NW 66.3 1.02E-07 l.3IE-07 2.08E-07
ToRap ( Khanh Son) N63.6 1.S6E-07 2.02E-07 3.20E-07
CamRanh NNE 62.4 4.6IE-07 6.03E-07 9.69E-07
LienNghia ( DucTrong ) WNW 78 8.03E-08 1.03E-07 1.63E-07
typically I37CS, to the total dose is clearly
proved.
- From table Ill: The effective dose for
the child is about 1.5 and 2 times, respectively,
greater than those for the teenager and adult.
Based on the calculation results for the
annual dose evaluations obtained from
analyzing the database and practical conditions
in the area around the NPP Ninh Thuan 1 we
can conclude that the gaseous effluent release
from the NPP satisfies the requirement on
radiation safety for population and production
activities in the normal operating condition.
IV. CONCLUSION
We have built the data inputs for two
computer codes XOQDOQ and GASPAR
based on collecting and processing a huge
database including the data on population and
population distribution for distinct age groups,
the data on agricultural production activities,
the terrain data and the meteorological data in
the five-year period 2009 - 2013.
The obtained calculation results for the
annual total population dose and the annual
individual dose at the specific locations within
the 80 km radius from the site of NPP Ninh
Thuan 1 showed that under a normal operation
scenario with the routine release of radioactive
nuclides from the NPP to the atmosphere all
15
We can see that the obtained results for
dose evaluation induced by the released
radioactive nuclides from the NPP Ninh Thuan
I are much lower than the permitted value of 1
mSv guided by NRC Regulations [7].
The annual individual dose values given
III
Table III show a quickly decreasing
tendency with respect to distance, for example
at Lien Nghia village which is nearly 80 km in
the WNW direction from the NPP site the dose
value is about 4 orders less than the dose at the
Vinh Tuong, near the NPP site.
From the obtained calculation results
shown in tables l-Ill we can see that:
- From table I: The dose induced by the
ground deposition gives the greatest
contribution, from 74.2% for thyroid to 93.6%
for bone, to the annual total population dose.
- From table II: The radioactive isotope
60Coinduces a greatest dose contribution, from
62 to 81%, tothe annual total population dose.
This is consistent with the real released data at
normal operation conditions, where the 60Co
isconsidered as a typical representative for the
radioactive nuclei produced from neutron-
induced activation reactions on the reactor core
materials and moderatorand released via
corrosion phenomenon [8]. Besides, the
contribution from the fission products,
ASSESSMENT OF RADIATION DOSE CAUSED BY RADIOACTIVEGASEOUS EFFLUENT ...
the dose values are much less than the
permitted limit of 1 mSv.
The
XJQ
value and
D/Q
value
distributions which are predominant in two
directions of North East and South West are
consistent with the wind rose distribution in the
80 km radius from the NPP site.
ACKNOWLEDGEMENT
This work has been performed in frame
work of the National Program on Science and
Technology in 2011-2015 Periodunder grant
no. KC-05.04111-15.
REFERENCES
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radiation", UNSCEAR Report YoU, (2000).
[2). "Radiation exposures in accidents", UNSCEAR
Report Vol.2, (2008).
[3]. J. F. Sagendorf, J. T. Goll, and W. F. Sandusky,
"XOQDOQ: Computer Program for the
Meteorological Evaluation of Routine Releases
at Nuclear Power Stations"; NUREG/CR-
2919;
Us.
Nuclear Regulatory Commission,
Washington, D.C; (1982).
[4). GAS PAR II - "Technical Reference and User
Guide, NUREG/CR-4653; D. L .Strenge, T.
1.
Bander, J.
K.
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l.l
09 - "Calculation of
Annual Doses to Man from Routine Releases
of Reactor Effluents for the Purpose of
Evaluating Compliance with 10 CFR" Part 50,
Appendix I;
Us.
Nuclear Regulatory
Commission, (1977).
[6). Regulatory Guide 1.111 - "Methods for
Estimation Atmospheric Transport and
Dispersion of Gaseous Effluents in Routine
Releases from Light - Water - Cooled
Reactor";
Us.
Nuclear Regulatory
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[7). Subpart D-"Radiation Dose Limits for
Individual Members of the Public"; Part 20-
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[8]. "Manual for Reactor Produced Radioisotopes",
IAEA-TECDOC-J340, P.O.Box 100, A-1400
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16
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H
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The
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instead
0
gamma
c
alternativ
which an
the
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Spectrum
us
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errors fre
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reduced.
In
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