Assessment of dose consequences based on postulated BDBA (beyond design basic accident) A-30MWt RSG-GAS after 30-year operation

Progress in Nuclear Energy 140 (2021) 103927

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Progress in Nuclear Energy
journal homepage: www.elsevier.com/locate/pnucene

Assessment of dose consequences based on postulated BDBA (beyond
design basic accident) A-30MWt RSG-GAS after 30-year operation
P.M. Udiyani, M.B. Setiawan *, M. Subekti, S. Kuntjoro, J.S. Pane, E.P. Hastuti, H. Susiati
BATAN, Center for Nuclear Reactor Technology and Safety, Puspiptek Region Gd.80 Serpong, Tangerang Selatan, 15310, Indonesia

A R T I C L E I N F O

A B S T R A C T

Keywords:
Dose
RSG-GAS
BDBA
Accident
EPZ

An assessment of the consequences of radiation doses due to the BDBA (beyond design basic accident) on the
RSG-GAS research reactor has been done. The assessment was carried out to evaluate the KNS (Serpong Nuclear
Area) EPZ (emergency preparedness zone) site after the reactor was operational for 30 years. The RSG-GAS
research reactor is a 30MWt multipurpose reactor. It is the largest research reactor in Indonesia. RSG-GAS
was built in the KNS Area in the Puspiptek complex which was put into operation in 1987. Previous estima­
tions of the radiological consequences were made on accidents which were postulated based on DBA conditions.
With the aging of the reactor, a study was carried out on the radiological consequences of the BDBA accident. The
ATWS (anticipated transient without scram) event caused the BDBA condition which resulted in the melted of 5

fuel bundles. Source term is estimated based on an inventory of 5 melted fuel bundles, and fission products
release through the reactor core, cooling system, reactor hall, and finally discharge to the environment through
the reactor stack. Radionuclide inventory is calculated by ORIGEN2.1. With the influence of weather, fission
products are dispersed into the air and deposited to the surface of the soil on the site. Weather and environmental
data used are spatial analysis of ARC-GIS. Consequences analysis was carried out in 16 wind direction sectors
within a 5 km radius using PC-COSYMA. The calculation results show the largest dose is reached in a radius
below 500 m with the direction of the wind to the South. The radiation dose is below the dose limits for the
exclusion and beyond exclusion area. Consequences of BDBA accident dose at RSG-GAS does not require
countermeasure like sheltering, evacuation nor relocation.

1. Introduction
The RSG-GAS research reactor was built in 1983. This research
reactor is located in the Serpong Nuclear Area (KNS) Puspiptek. It
reached its first critical level in July 1987. In March 1992 the reactor
operated at a nominal power of 30 MW. The permit to extend the
operation until 2030 was issued by Bapeten Indonesian nuclear regu­
latory body, on December 6, 2020.
RSG-GAS is a pool type reactor designed as a medium power research
reactor (30 MW). It is located in the Center for Science and Technology
Research (PUSPIPTEK) Serpong, South Tangerang. This site is located at
6◦ 21′ 40′′ south latitude, 106◦ 39′ 57′′ east longitude and about 60 m
above sea level. The reactor site is surrounded by several villages and the
Cisadane river as the western boundary.
Puspiptek area which has an area of 3.5 square kilometer. It is
located in Setu village, Cisauk sub-district, Tangerang district, Banten
province. The Puspiptek area is about 27 km southwest of the

metropolitan city of Jakarta, and the distance from the site to the sea
area, namely the Java Sea, is about 36 km.
The type of fuel is a plate with low uranium enrichment (19.75 %). In

the year of 2005, its fuel - which was originally Uranium Oxide – was
changed to Uranium Silicide (U3Si2–Al). The number of fuel elements in
the reactor core is 40 fuel elements (FEs) and 8 control elements (CEs)
(BATAN, 2019). Coolant and moderator of reactors is light water (H2O)
with a Berylium reflector. RSG-GAS is a multipurpose reactor used
mainly for neutronical, thermohydraulic, reactor safety system, power
reactor research, and radiation protection. It is also used for the pro­
duction of radioisotopes and silicon dopping, advanced material irra­
diation and for Neutron Activation Analysis (NAA).
The operation of the RSG-GAS has the consequence of radioactive
discharge into the environment. Radioactive releases into the environ­
ment from the operation of nuclear reactors occur under normal or
abnormal operating conditions. Radioactive releases through the reactor
stack will spread in the atmosphere and deposited to the ground surface.

* Corresponding author.
E-mail address: (M.B. Setiawan).
/>Received 21 January 2021; Received in revised form 25 June 2021; Accepted 9 August 2021
Available online 14 August 2021
0149-1970/© 2021 The Authors.
Published by Elsevier Ltd.
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P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

With the influence of weather and local meteorological conditions, this
radioactive substance is spread and through various pathways of expo­
sure into the human body. The Safety Analysis Report (SAR) document
from the RSG-GAS and the study of the radiological consequences of the
reactor operating in normal conditions and postulated DBA accidents
have been carried out by several researchers (Udiyani et al., 2018a;
Kuntjoro and Udiyani, 2005).
The results of the study of the consequences of normal conditions are
used as a basis for environmental monitoring of the KNS site. While the
results of the study of the consequences of the accident are used as a
nuclear emergency in the KNS region. In accordance with SAR and the
Bapeten regulatory body considerations, nuclear emergency zones
within the site and outside the site are monitored within a 5 km radius. A
500 m exclusion zone is determined and emergency areas outside the
exclusion zone up to 5 km. The determination of the emergency zone is
estimated based on the DBA accident postulation, which is an accident

resulting from the melting of a bundle of fuel elements. The assumption
is that there has been an accident that is the damage of a set of fuel el­
ements (equal to 21 plates of the fuel element). The accident caused by a
blockage of the cooling channel. These accidents resulted fission product
nuclides regardless of the cladding of fuel into the cooling system with a
particular faction. Part of the nuclide is released from the cooling water/
reactor tank into the reactor chamber. Finally a small portion of radio­
nuclides can be released from the reactor chamber into the atmosphere
(BATAN, 2019; Kuntjoro and Udiyani, 2005; Hastowo, 1996)
Since the accident of the Dai-ichi Fukushima reactor, the IAEA and
the regulatory body of the nuclear reactor owner re-review the safety of
existing reactors and those are not yet operated. The review was carried
out by adding a study of radiation impacts to severe accidents or BDBA
(Arjun et al., 2014; Mehbooba et al., 2015; Raimond et al., 2013).
Learning from the Fukushima accident and the aging of the RSG-GAS
which is already 30 years old, a study of the radiological conse­
quences to be included in the SAR were done based on the BDBA acci­
dent. Based on the dissertation of Hudi Hastowo (1996) (Hastowo,
1996), BDBA conditions are surrounded by reactor thermohydraulic
calculations based on the ATWS (Anticipated Transient Without Scram).
ATWS is triggered by the blockage of the coolant flow in the fuel. The
simulation results obtained a state where 5 fuel bundles melt (BATAN,
2019; Hastowo, 1996). Based on these conditions the inventory and
source term of the BDBA accident are calculated. With meteorological
influences and site environmental data within a 5 km radius, it can be
determined the activity of fission products that are dispersed in the at­
mosphere and deposited on the surface of the site. With various path­
ways that are adapted to local data and conditions, receipt of doses and
emergency zoning can be estimated. Calculation of inventory of fission
products in fuel or reactor core using ORIGEN 2.1 (Rahgoshay and

Hashemi-Tilehnoee, 2013; Obaidurrahman and Gupta, 2013; Setiawan
et al., 2020; Kuntjoro et al., 2019). Meteorology and environmental data
are processed with software for spatial analysis, ARC-GIS. Estimation of
radiologic consequences in the environment using PC-Cosyma software
based on the atmospheric dispersion model (Udiyani et al., 2016;
Udiyani et al., 2018b; Cao et al., 2000; Udiyani et al., 2019; European
Commission, 1995).

in the atmosphere, deposited on the ground surface, and through various
pathways into the human body. Zoning of nuclear emergencies is
determined based on the receipt of public and environmental doses. The
methodological approach to calculating radiation consequences is
shown in Fig. 1.
2.1. Radioactivity source term
The source term calculation is based on a BDBA accident that was
simulated in the RSG-GAS. The worst accident condition which was
simulated in the reactor thermo-hydraulic calculation based on the
ATWS condition which was triggered by the blockage of the coolant flow
in the fuel. This condition causes 5 fuel elements to melt (Hastowo,
1996). Calculation of inventory of fission products on 5 melted fuels
using ORIGEN 2.1. The calculation is done based on the neutral pa­
rameters of the fuel. Fuel material from U3Si2Al; Cladding material from
AlMg3; Channel width is 2.55 mm; The number of U-235 per element of
fuel is 250 g; Fuel dimensions (0.54 x 62.75 × 600 mm); U-235
Enrichment is 19.75 %; Uranium density in fuel (2.96 g/cm3). With a
new fuel management pattern, the five melting fuel elements are the
F-26, F-31, F-32, F-36, and F-37 with burn-up respectively 37.94 %,
32.55 %, 44.82 %, 40.90 % and 20.81 % as seen in Fig. 4 (Setiawan et al.,
2020; Kuntjoro et al., 2019).
Radionuclide activity that can reach the reactor stack is obtained

from the following equation:
QS = Q1 + Q2 = (0.4 × f1 × f2 × f3 × A) + (0.6 × f1 × f2 × f3 × (1 − ηA ) × A)
(1)
Where A is an inventory activity (Bq); Q1 is radionuclide activity in
cooling water (Bq); Q2 is radionuclide activity released into the reactor
hall (Bq); f1 is radionuclide fraction that can escape from the fuel going
to the cooler; f2 is radionuclide fraction that can release from the coolant
to the reactor chamber; f3 = iodine fraction; and η = efficiency of reactor
stack filters. The values of f1 and f2 for noble gases are 1.0 and the Br
nuclides are 5 × 10− 4. The value of f1 is 0.5 for iodine (element or
organic) or other nuclides. The f2 values for the Iodine element are 5 ×
10− 4 and 5 × 10− 2 for organic Iodine. The value of f 2 for other nuclides
is 1 × 10− 5. The release fraction f3 for iodine (element or organic) is 0.5.
The efficiency of the stack filter for noble gases is 0.0. The efficiency of
the stack filter for Br and Iodine elements is 0.99 and for organic iodine
or other nuclides is 0.90 (BATAN, 2019; Kuntjoro and Udiyani, 2005).
2.2. Radioactivity and radiological concequences
Estimates for radioactivity of atmospheric dispersion and surface
deposition use the segmented Gaussian equation default from PCCosyma (European Commission, 1995). It uses a segmented Gaussian
plume model which allows for hourly changes in the wind speed and
direction, stability category and rainfall rate affecting the dispersing
material. The segmented plume model Musemet incorporated in
PC-Cosyma was employed for the calculations; it is an improved linear
Gaussian plume model, which assumes that the meteorological condi­
tions (wind direction, wind speed, stability category and rain intensity)
are known and constant in subsequent time intervals of 1 h (European
Commission, 1995; Panitz et al., 1989).
The segmented Gaussian plume model allowing of atmospheric
conditions and wind direction will changes during plume travel. This
model derives the sequences of atmospheric conditions affecting the

plume from a data file giving hourly averages for wind speed and di­
rection, stability category, precipitation intensity and mixing layer
depth. The linear Gaussian for atmospheric dispersion shown in
following equation

2. Methodology
Study of the consequences of environmental and community has
based on radiology atmospheric disperse (Pirouzmand et al., 2015;
Birikorang et al., 2015; Abdelhady, 2013; Hirose, 2016). The calculation
mechanism starts from the calculation of fuel inventory, and source term
is calculated based on inventory data. Fission products released to the
primary cooling water system through the reactor pool passes to the
reactor hall and reactor building. It is assumed that fission products
release into the atmosphere as source term without going through stack
filters.
Due to the influence of meteorology, the plume formed is dispersed
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P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

Fig. 1. Methodology approach of radiological consequences calculation.

Q [
KNS. Data were taken every hour for one year for 16 wind direction
sectors. Wind rose of KNS area is depicted in Fig. 2.
2πσy σ z μ
/ ( / ) ]{ [

/
]
[
/
]}
As seen in Fig. 2, the dominant wind direction blows towards the
2
2
2
− 1 2 y σy
exp − 1 2((z − H)/σ z ) + exp − 1 2((z + H)/σz )
south (occurrence frequency is about 28 %) with a dominant speed
(2)
between 2.4 and 3.8 m/s (occurrence frequency is around 8 %). Sta­
bilities: 29.0 % stability D; 26.0 % stability E; 18 % stability F, and 27 %
Where X (x,y,z) = Concentration in the air (chi) on the x-axis, y, z (Bq.s/
stability C rain.
3
m ): Q = Source term (Bq): μ = Wind speed (m/s): σy = Horizontal
Calculation of radiation doses through four main pathways are
dispersion coefficient (m): σz = Vertical dispersion coefficient(m): H =
external gamma and beta from cloud shine, external gamma from sur­
Effective height (m): y = Distance perpendicular to the wind (m): z =
face ground, inhalation of cloud shine, and ingestion of contaminated
Height above ground (m).
food, as illustrated in Fig. 3. Local production data or agriculture and
Generally, with respect to Gaussian dispersion modelling, atmo­
livestock such as grain products, leafy vegetable, non-leafy vegetable,
spheric turbulence is classified by empirical turbulence-typing schemes.
root vegetable, milk, meat cow and sheep meat are taken for 16 wind

The most widely used scheme is the one developed by Pasquill and
directions for 9 radius distances (500 m; 1.0 km; 1.5 km; 2.0 km; 2.5 km;
Gifford (European Commission, 1995; Panitz et al., 1989), which assigns
3.0 km; 3.5 km; 4.0 km; and 4.5 km).
the grade of atmospheric stratification to six diffusion categories. Class A
corresponds to very unstable conditions and is associated with small
2.3. Countermeasure
mechanical but large thermal components of turbulence. Class B is
moderately unstable and Class C is slightly unstable. Class D represents
Anticipatory actions are carried out according to certain criteria and
the neutral atmospheric conditions and turbulence is only due to the
the time and duration of the action based on the dose exposed in the
mechanical component. Class E is moderately stable, and Class F cor­
location area. A dose-based evacuation measure is taken if the com­
responds to thermally very stable conditions and the mechanical tur­
munity receives a total effective body dose >0.05 Sv, that is, the dose
bulence tends to be damped by buoyant forces (Panitz et al., 1989).
can cause non stochastic effects. While sheltering is for receiving doses
Meteorological data such as weather stability, wind direction, wind
between 0.02 and <0.05 Sv, and the dose received for Iodine tablets is
speed and solar radiation are taken from the latest data (2016) from the
0.02 Sv (Publication 10, 2007; BAPETEN, 2013). Restrictions on the

χ (x, y, z) =

3


P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

Fig. 2. Wind rose in the KNS area of RSG-GAS site.

8 %, 40 % and 40 %. While for the new fuel management pattern is the
F-26, F-31, F-32, F-36 and F-37 with burn-up respectively: 37.94 %,
32.55 %, 44.82 %, 40.90 % and 20.81 %.
The condition of the five melted fuels is simulated for the calculation
of the worst accident condition source term. Each fuel element and
control element consist of 21 and 15 U3Si2–Al fuel plates with a 19.75 %
uranium enrichment. In the old fuel management pattern, the reactor
core consists of 7 burn-up classes with an 8 % burn-up class and 6/1
fuel/control replacement pattern for 6 cycles and 6/2 fuel/control in the
7th cycle and over every 7 cycles. As for the new fuel management
pattern, the reactor core consists of 8 burn-up classes with a 6.20 %
burn-up class. The reactor core replacement pattern is 5/1 fuel/control
element per cycle.
From Fig. 4, it can see that in each box, the first line shows the type of
fuel of FE or CE, the second line depicts the burn-up fraction in BOC (%)
and the third line states the Power Peaking Factor (PPF) in FE or CE.
RSG-GAS reactor has 4 Central Irradiation Position (CIPs) of and also 4
Irradiation Position (IPs). CIP and IP are intended for material irradia­
tion for research purpose as well as for the radioisotope production.
After the fuel melted is determined, an inventory calculation is done
for each management pattern for each of the five fuels using the
ORIGEN-2.1. For the nuclear library, the Thermal Library embedded in
ORIGEN-2 is used. The inventory calculation was carried out for FE with
1 fresh FE consisting of 0.25 kg of U3Si2–Al with an enrichment of 19.75
%. Burn-up calculation is carried out with a combustion power of {30
MW/[40 + ((15/21) × 8)]} × {PPF of each FE} for 25 days (1 cycle of

operation).
Inventory calculations use melt pattern based on new management,
since it provides more pessimistic inventory activities. Source term
calculations using mechanism approach do not involve filtering in filter
stack. Assumptions without a stack filter will be obtained from pessi­
mistic source terms.
Calculation results for inventory of 5 melted fuel and BDBA accident
postulation source term, shown in Table 1. Inventory of reactor fuels is
classified into 8 groups, namely: the noble gas group (Cr, Xe); Halogen
Group (I, Br); Alkali group metal (Cs); the Tellurium group (Te and Sb);
Strontium and Barium (Sr, Ba); Noble metal (Ru and Rh); Lanthanide

Fig. 3. Four main pathways are external gamma and beta from cloud shine,
external gamma from surface ground, inhalation of cloud shine, and ingestion
of contaminated food.

consumption of local food (food bans) are determined based on the dose
received from contaminated agricultural and livestock products.
3. Results and discussions
3.1. Reactor core inventory and source term of BDBA
The RSG-GAS equilibrium core consists of 40 Fuel Elements (FEs)
and 8 Control Elements (CEs), arranged in 6 burn-up classes with each
BU class representing the burn-up fraction of 8 % (Kuntjoro et al., 2019).
Old fuel management patterns that melt is FE-26 (Fuel element-26),
FE-31, FE-32, FE-36 and FE-37 with burn-up successive 16 %, 48 %,
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P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

Fig. 4. Equilibrium core for new fuel management patterns.
Table 1
Fuel inventory and source terms for BDBA postulation of RSG-GAS.
Radionuclide group

Nuclide

Fuel Inventory (Bq)

Source term (Bq)

Radionuclide group

Nuclide

Fuel Inventory (Bq)

Source term (Bq)

Noble Gas

Kr-85
Kr-85m
Kr-87
Kr-88
Xe-133
Xe-135
I-131

I-132
I-133
I-134
I-135
CS-134
CS-137
Rb-88
Te-132
Sb-125
Sb-127

8.38E+12
6.31E+14
8.64E+14
1.63E+15
3.89E+15
6.27E+14
1.65E+15
2.48E+15
3.92E+15
4.40E+15
3.66E+15
1.82E+13
6.91E+13
2.09E+15
2.47E+15
8.00E+13
8.00E+13

8.38E+12

6.31E+14
8.64E+14
1.63E+15
3.89E+15
6.27E+14
4.11E+11
6.20E+11
9.79E+11
1.10E+12
9.15E+11
9.08E+07
3.45E+08
1.05E+10
1.23E+10
4.00E+08
4.00E+08

Strontium and Barium

Sr-89
Sr-90
Ba-139
Ba-140
Ru-105
Ru-106
Rh-103m
Rh-105
La-140
Y-90
Y-91

Nb-95
Pr-143
Nd-147
Ce-141
Ce-143
Ce-144

3.34E+15
6.66E+13
3.74E+15
3.62E+15
6.44E+14
1.16E+14
2.01E+15
5.36E+14
3.68E+15
7.15E+13
4.04E+15
4.30E+15
3.39E+15
1.31E+15
4.01E+15
3.42E+15
1.81E+15

1.67E+10
3.33E+08
1.87E+10
1.81E+10
3.22E+09

5.82E+08
1.00E+10
2.68E+09
1.84E+10
3.57E+08
2.02E+10
2.15E+10
1.69E+10
6.56E+09
2.01E+10
1.71E+10
9.06E+09

Halogen

Alkali Metal
Tellurium

Noble Metal

Lanthanides

Cerium

Table 2
Mean concentration of nuclides on air or on ground surface.
Distance (km)
0.500
1.000
1.500

2.000
2.500
3.000
3.500
4.000
4.500

Noble gas

Halogen

Alkali metal

Other Nuclide

Air Bq.s/m3

ground Bq/m2

air Bq.s/m3

ground Bq/m2

air Bq.s/m3

ground Bq/m2

air Bq.s/m3

ground Bq/m2

1.93E+10
6.37E+09
3.35E+09
2.01E+09
1.44E+09
1.24E+09
1.07E+09
9.35E+08
7.67E+08

0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00

7.01E+08
2.01E+08
9.58E+07
5.82E+07
4.07E+07
3.35E+07
2.78E+07
2.40E+07
1.94E+07

6.93E+06
1.99E+06
9.45E+05
5.73E+05
4.01E+05
3.30E+05
2.73E+05
2.36E+05
1.91E+05

1.07E+05
3.40E+04
1.75E+04
1.10E+04
8.09E+03
7.08E+03
6.31E+03
5.62E+03
4.64E+03

1.07E+02
3.40E+01
1.75E+01
1.10E+01
8.09E+00
7.08E+00
6.31E+00
5.62E+00
4.64E+00

3.37E+06
1.08E+06
5.56E+05
3.46E+05
2.53E+05
2.27E+05
1.94E+05
1.72E+05
1.41E+05

3.37E+03
1.08E+03
5.56E+02
3.46E+02
2.53E+02
2.19E+02
1.94E+02
1.72E+02
1.41E+02

5


P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

Group (La, Y, Nb, Pr, N and Sm), and Cerium Group (Ce) (Yangmo et al.,
2014; Herranza et al., 2015).

Table 3
Dose Consequences of RSG-GAS BDBA accidents.
Distance
(km)

3.2. Radioactivity on air dispersion or surface deposition
The results of the calculation of radioactivity disperse in the air and
disposition on the surface are listed in Table 2. Nuclear radioactivity is
grouped in 4 types, namely: Nuclides from noble gas (Xe, Kr); Alkali
metal (Cs, Rb); Halogen (I); and Other Nuclide (Sr, Y, Te, Nb, Pr, Ce, Nd,
Ba, La, Ru, Sb and Zr).
Table 2 shows the averaged radioactivity in atmospheric air for each
radius. The highest activity that is dispersed in sector 9 is the sector that
has a radial angle deviation ±202.50 from the North. From the data it
can also be seen that for the same nuclide, radioactivity decreases with
increasing radius of the RSG-GAS. The highest radioactivity is at a radius
of 500 m, while the lowest is at a radius of 4.5 km from the release
center.
Radioactivity in the air affects the contribution of radiation doses
that human receive from inhalation exposure pathways and direct
exposure from the air (cloudshine). The highest radioactivity in the air
and at ground level (except for noble gases) occurs in a 500 m radius
area from the center of release. The highest total radionuclides in the
noble gas group (Xe and Kr) are 1.93E+10 Bq.s/m3; from group Halogen
is 7.01E+08 Bq.s/m3; and 1.07E+05 Bq.s/m3 from the Alkali metal
group; as well as from other nuclides groups of 3.37E+06 Bq.s/m3.
Although the highest radioactivity in the air is in the noble gas group,
but generally noble gas have a short half-life. The shortest half-life of
noble gas is Kr-87 (1.3 h), Kr-88 (2.8 h), Cr-85m (4.5 h), Xe-133 (5.27

days), and the longest is Xe-135 (9.1 days). Since the half-life is short
and cannot react with matter (inert), then the accumulation effect is
small. This results in the contribution to the radiation dose not being too
large when compared with radionuclides which have a long half-life or
from radionuclides which are not a noble gas group. For the dispersion
in the air the highest radionuclide activity comes from the noble gases.
Since it is inert, then the noble gas will not be deposited at the soil
surface.
From Table 2, it can be seen that the highest radioactivity of depo­
sition is from the Halogen group or the Iodine group, which is equal to
6.93E+06 Bq/m2. Nuclei I-131 will gradually be disposed to ground and
plants which will then enter the food chain towards livestock and
humans. These nuclides in addition to donating internal doses through
food and inhalation, also contributors to external doses through the
ground surface and radioactive clouds. Its effect on internal dosages in
plant consumption from fruit is not too large because the half-life is
relatively short (8.04 days) compared to the time of plant growth. A
significant contribution to the radiation dose from radionuclide depo­
sition comes from Cs-137 radionuclide. The long half-life is 30.17 years,
making additional doses of the effects of accumulation from the food
chain.

0.500
1.000
1.500
2.000
2.500
3.000
3.500
4.000

4.500

Mean Individual dose
effective (Sv)

Mean Individual dose
of thyroid (Sv)

Shortterm

Longterm

Shortterm

Longterm

1.31E03
5.12E04
2.85E04
1.86E04
1.46E04
1.34E04
1.03E04
9.38E05
8.12E05

2.44E03
1.17E03
6.82E04
4.68E04

3.59E04
3.17E04
2.32E04
2.00E04
1.78E04

1.47E03
5.74E04
3.20E04
2.00E04
1.64E04
1.50E04
1.16E04
1.05E04
9.13E05

2.68E04
1.02E04
5.59E05
3.62E05
2.83E05
2.57E05
1.99E05
1.81E05
1.56E05

Collective dose
(man.Sv)

2.01E+00

2.30E+00
3.72E-06
4.57E+00
2.89E-06
1.67E+00
6.98E-07
7.43E-01
1.32E-07

the center of detachment, that is 4.57E+00 man-Sv. The effective indi­
vidual dosage received is still below to the recommended dose limit of
the Bapeten regulatory body for the general public (BAPETEN, 2013).
3.4. Countermeasure
Countermeasures are carried out, based on estimated radiation doses
received by the public at the Serpong Nuclear Area (KNS) site. Based on
the dosage data in Table 3, no countermeasure action were taken. Dose
data in Table 3 showed that the short-term dose not meet the criteria for
Iodine tablet blocking to 0.02 Sv dose; sheltering for receiving doses
exceed 0.01Sv; and for evacuation if the dose exceeds reception 0.05 Sv.
From the results of research for BDBA condition, the emergency zoning
of the Serpong nuclear area (KNS) is not significantly different from the
emergency zoning made based on the DBA accident. Communities
around KNS in the same zoning of DBA and BDBA received radiation
doses for countermeasure criteria that were not different. i.e. there is no
need for particular action of giving iodine tablets, sheltering, or
evacuation.
4. Conclusions
In this study, the consequences of RSG-GAS doses with a power of 30
MWt after 30 years of operation are evaluated based on BDBA postula­
tion. The study was conducted using the latest input data of BDBA source

term and meteorology data, population data, environmental data in
2016. The calculation resulted in the maximum effective dose received
in sector 9 (southward) within a radius of 0.5 km from the reactor. The
maximum short-term effective individual dose received is 1.31E-03 Sv,
under the Bapeten regulatory body’s accident limits for the exclusion
area of 0.25 Sv, and the limit of 0.005 Sv for certain conditions for the
community. The study results also state that countermeasure measures
such as Iodine tablet blocking, sheltering, and evacuation, are not
needed.

3.3. Dose consequences
The results of the calculation of short-term doses of the external
exposure and inhalation received by the community around the RSGGAS (within a 5 km radius) are in Table 3. Based on the distance of
acceptance, the dose is reduced by increasing the radius from the
reactor. The maximum short-term individual effective dose is 1.31E-03
Sv, and 2.44E-03 Sv for long-term dose respectively. This dose value is
below the maximum limit for the exclusion area of 0.25Sv (Publication
10, 2007), and the limit of 0.005 Sv for certain conditions for the public
(BAPETEN, 2013).
The amount of dose received is proportional to the activity of
radioactive dispersion and deposition. Meteorological conditions will
determine the dispersion model that occurs, it will then affect the drop
site and surface deposition.
The largest collective dose is found in an area at a radius of 2 km from

Declaration of competing interest
The authors declare that they have no known competing financial
interests or personal relationships that could have appeared to influence
the work reported in this paper.

6


P.M. Udiyani et al.

Progress in Nuclear Energy 140 (2021) 103927

Acknowledgement

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This work is conducted with 2019 research funding of the Center for
Nuclear Reactor Technology and Safety (PTKRN), BATAN. It is also
partially supported by 2018–2019 National Research Incentive RISTEKDIKTI and 2020 LPDP Ministry of Finance Incentive Program. Thanks to
all colleagues in the Center for Multipurpose RSG-GAS who have pro­
vided technical assistance related to this research.
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