Budi Setiawan - Academia.edu (original) (raw)

Papers by Budi Setiawan

Research paper thumbnail of Estimation of core inventory for PWR 160MWt

THE 4TH INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICoNETS) 2021

Estimation of Core inventory simulation for PWR 160MWt has been done. Core inventory is one of th... more Estimation of Core inventory simulation for PWR 160MWt has been done. Core inventory is one of the parameters related to the release of radioactive materials be used as data for further calculation or analysis related to nuclear safety. PWR 160 MWt has a core configuration consist of 37 fuel assemblies with three types of Uranium enrichment of the fuel. Core fission product inventory calculation was performed using ORIGEN2.1 by assuming the reactor irradiated for 2 years (fuel cycle) without cooling time. Simulation results in many radionuclides, some nuclides have long decay times (e.g. Cs-135; Cs-137), some have short-lived (e.g. I-136, Xe-140), some have high radioactivity (e.g. Xe-133; I-134) and some nuclides indicate a significant contribution to determining source term (e.g. I-131; Cs-137). Simulation results obtained can be used for further calculations for safety analysis such as determination of source term, dose calculation, and precautions to minimize the occurrence of radioactive to the environment.

Research paper thumbnail of Calculation of Radioactive Source Term Release from Flexblue NPP

One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Re... more One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Research and Technology for the period of 2020-2024 is small modular reactor (SMR) nuclear power plant (NPP) assessment. The France’s Flexblue is a PWR-based SMR submerged reactor with a power of 160 MWe. The Flexblue reactor module was built on the ocean site and easily provided the supply of reactor modules, in accordance with the conditions of Indonesia as an archipelagic country. Therefore, it is necessary to know the release of fission products (source term), which is necessary for the study of the radiation safety of a nuclear reactor. This paper aims to examine the source term in normal operating conditions and abnormal normal operating conditions, as well as postulated accidents. Based on the Flexblue reactor core parameter data, the calculation of the reactor core inventory uses the ORIGEN2 software is previously evaluated. The source term calculation uses a mechanistic approach a...

Research paper thumbnail of Evaluation on transmutation of minor actinides discharged from PWR spent fuel in the RSG-GAS research reactor

Malaysian Journal of Fundamental and Applied Sciences, 2019

The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its ef... more The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its effectiveness to transmute minor actinides (MA), specifically Am-241, to support geologic storage/disposal. The Am-241 radionuclide was assumed to be discharged from 1000MWe PWR’s spent fuel. The mass of Am-241 discharged from within a year operation of 1000MWe PWR was 1.65E+03 gram, while the optimum Am-241 mass which can be transmuted in RSG-GAS - and still meet the safety requirements of reactivity - was 8.0E+03 gram. This was equivalent to about cumulative Am-241 discharged from 5 units of 1000MWe PWR. In 10 cycles of RSG-GAS operation (about 2 years), the remaining of Am-241 is only about 100 grams. The ratio of Am-241 transmuted (8.0E+03 gram) and Am-241 produced in the RSG-GAS core (1.98E-02 gram) within 1-year operation shows the effectiveness of RSG-GAS as a transmutation reactor.

Research paper thumbnail of Analysis on Transmutation of Long-Lived Fission Products from PWR Spent Fuel Using the 30-MW(thermal) RSG-GAS Reactor

Nuclear Technology, 2020

The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effec... more The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effectiveness for transmuting long-lived fission products (LLFPs), particularly 129 I and 99 Tc. Both radionuclides selected are assumed as discharged from of a 1000-MW(electric) pressurized water reactor (PWR) spent fuel. If these radionuclides are stored in sustainable geologic disposal, they will require high-cost handling due to their special shielding. In one cycle of PWR1000 operation, the 99 Tc produced is 43.7 kg and 129 I is 9.5 kg in its spent fuel. Considering reactor safety, the maximum target mass permitted to be transmuted in the RSG-GAS is 3.0 kg for the 99 Tc and 5.0 kg for the 129 I. In 1 year of (five cycles) operation, the 99 Tc and 129 I targets would be reduced by 126 and 290 g, respectively. Although it has the potentiality to safely transmute LLFP targets in its core, RSG-GAS requires longer irradiation time (about 20 years) to entirely transmute the targets.

Research paper thumbnail of Evaluation of radionuclide inventory in the CAREM-25 small modular reactor

AIP Conference Proceedings, 2019

CAREM-25 is an Argentina national nuclear power plant project based on PWR technology. It is desi... more CAREM-25 is an Argentina national nuclear power plant project based on PWR technology. It is designed as a small modular reactor (SMR) of 100MWt which has more flexibility in its construction and maintenance. SMR-type power plant is considered suitable to be deployed in archipelagoes country such as Indonesia. For the purpose of safety analysis, it is necessary to calculate radionuclide inventory from the reactor core under operating conditions. The radionuclide inventory of materials irradiated in a reactor depends on the initial material composition, burn-up history and the power peaking factor. The purpose of the present work is to evaluate radioanuclide inventory in fuel materials of CAREM-25 in the normal operational condition. ORIGEN-2 code was used through the calculation. The computational result of the relative contribution to the total radionuclide inventory of CAREM-25 is: Halogen group has the largest activity of 2.089E+07 Ci (~7.729E+17 Bq), the other groups are: the Rare Gases group (Kr and Xe) is about 8.499E+06 Ci (~3.144E+17 Bq); Alkali metal (Cs) group is 1.

Research paper thumbnail of Evaluation of Fuel Burn-up and Radioactivity Inventory in the 2 MW TRIGA-Plate Bandung Research Reactor

Journal of Physics: Conference Series, 2019

Currently plate-type fuels are planned to use in the research reactor TRIGA-2000 Bandung, Indones... more Currently plate-type fuels are planned to use in the research reactor TRIGA-2000 Bandung, Indonesia (further called as TRIGA-Plate reactor). Plate type fuel consists of enriched uranium sandwiched between metal cladding. Plate-type fuel is used in some research reactors to obtain high neutron flux and is used to study material irradiation or isotope production. For the purpose of Safety Analysis Report (SAR) on the fuel-type modification plan of TRIGA-2000 Bandung, it is necessary to calculate radioactivity inventory from the reactor core under operating conditions. The radioactivity inventory of materials irradiated in a reactor depends on the initial material composition at the BOC, burn-up history from BOC to EOC and the power peaking factor. The purpose of the present work is to evaluate the fuel burn-up and radioactivity inventory in fuel materials of TRIGA-Plate research reactor. The mass of U-235 consumed and the mass of Pu-239 and Th-232 produced are also evaluated. The calculation results obtained using ORIGEN2 code are: the mass of U-235 consumed is 1.40E+02 gram; while the mass of Pu-239 produced is 1.36E+00 gram and Th-232 produced is 1.03E-06 gram. The largest radioactivity inventories of the reactor at the EOC sequentially are: Kr group is about 2.29E+02 Ci; for group I is 7.77E+03 Ci and for groups Cs is 1.92E+02Ci.

Research paper thumbnail of Estimation of core inventory for PWR 160MWt

THE 4TH INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICoNETS) 2021

Estimation of Core inventory simulation for PWR 160MWt has been done. Core inventory is one of th... more Estimation of Core inventory simulation for PWR 160MWt has been done. Core inventory is one of the parameters related to the release of radioactive materials be used as data for further calculation or analysis related to nuclear safety. PWR 160 MWt has a core configuration consist of 37 fuel assemblies with three types of Uranium enrichment of the fuel. Core fission product inventory calculation was performed using ORIGEN2.1 by assuming the reactor irradiated for 2 years (fuel cycle) without cooling time. Simulation results in many radionuclides, some nuclides have long decay times (e.g. Cs-135; Cs-137), some have short-lived (e.g. I-136, Xe-140), some have high radioactivity (e.g. Xe-133; I-134) and some nuclides indicate a significant contribution to determining source term (e.g. I-131; Cs-137). Simulation results obtained can be used for further calculations for safety analysis such as determination of source term, dose calculation, and precautions to minimize the occurrence of radioactive to the environment.

Research paper thumbnail of Calculation of Radioactive Source Term Release from Flexblue NPP

One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Re... more One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Research and Technology for the period of 2020-2024 is small modular reactor (SMR) nuclear power plant (NPP) assessment. The France’s Flexblue is a PWR-based SMR submerged reactor with a power of 160 MWe. The Flexblue reactor module was built on the ocean site and easily provided the supply of reactor modules, in accordance with the conditions of Indonesia as an archipelagic country. Therefore, it is necessary to know the release of fission products (source term), which is necessary for the study of the radiation safety of a nuclear reactor. This paper aims to examine the source term in normal operating conditions and abnormal normal operating conditions, as well as postulated accidents. Based on the Flexblue reactor core parameter data, the calculation of the reactor core inventory uses the ORIGEN2 software is previously evaluated. The source term calculation uses a mechanistic approach a...

Research paper thumbnail of Evaluation on transmutation of minor actinides discharged from PWR spent fuel in the RSG-GAS research reactor

Malaysian Journal of Fundamental and Applied Sciences, 2019

The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its ef... more The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its effectiveness to transmute minor actinides (MA), specifically Am-241, to support geologic storage/disposal. The Am-241 radionuclide was assumed to be discharged from 1000MWe PWR’s spent fuel. The mass of Am-241 discharged from within a year operation of 1000MWe PWR was 1.65E+03 gram, while the optimum Am-241 mass which can be transmuted in RSG-GAS - and still meet the safety requirements of reactivity - was 8.0E+03 gram. This was equivalent to about cumulative Am-241 discharged from 5 units of 1000MWe PWR. In 10 cycles of RSG-GAS operation (about 2 years), the remaining of Am-241 is only about 100 grams. The ratio of Am-241 transmuted (8.0E+03 gram) and Am-241 produced in the RSG-GAS core (1.98E-02 gram) within 1-year operation shows the effectiveness of RSG-GAS as a transmutation reactor.

Research paper thumbnail of Analysis on Transmutation of Long-Lived Fission Products from PWR Spent Fuel Using the 30-MW(thermal) RSG-GAS Reactor

Nuclear Technology, 2020

The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effec... more The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effectiveness for transmuting long-lived fission products (LLFPs), particularly 129 I and 99 Tc. Both radionuclides selected are assumed as discharged from of a 1000-MW(electric) pressurized water reactor (PWR) spent fuel. If these radionuclides are stored in sustainable geologic disposal, they will require high-cost handling due to their special shielding. In one cycle of PWR1000 operation, the 99 Tc produced is 43.7 kg and 129 I is 9.5 kg in its spent fuel. Considering reactor safety, the maximum target mass permitted to be transmuted in the RSG-GAS is 3.0 kg for the 99 Tc and 5.0 kg for the 129 I. In 1 year of (five cycles) operation, the 99 Tc and 129 I targets would be reduced by 126 and 290 g, respectively. Although it has the potentiality to safely transmute LLFP targets in its core, RSG-GAS requires longer irradiation time (about 20 years) to entirely transmute the targets.

Research paper thumbnail of Evaluation of radionuclide inventory in the CAREM-25 small modular reactor

AIP Conference Proceedings, 2019

CAREM-25 is an Argentina national nuclear power plant project based on PWR technology. It is desi... more CAREM-25 is an Argentina national nuclear power plant project based on PWR technology. It is designed as a small modular reactor (SMR) of 100MWt which has more flexibility in its construction and maintenance. SMR-type power plant is considered suitable to be deployed in archipelagoes country such as Indonesia. For the purpose of safety analysis, it is necessary to calculate radionuclide inventory from the reactor core under operating conditions. The radionuclide inventory of materials irradiated in a reactor depends on the initial material composition, burn-up history and the power peaking factor. The purpose of the present work is to evaluate radioanuclide inventory in fuel materials of CAREM-25 in the normal operational condition. ORIGEN-2 code was used through the calculation. The computational result of the relative contribution to the total radionuclide inventory of CAREM-25 is: Halogen group has the largest activity of 2.089E+07 Ci (~7.729E+17 Bq), the other groups are: the Rare Gases group (Kr and Xe) is about 8.499E+06 Ci (~3.144E+17 Bq); Alkali metal (Cs) group is 1.

Research paper thumbnail of Evaluation of Fuel Burn-up and Radioactivity Inventory in the 2 MW TRIGA-Plate Bandung Research Reactor

Journal of Physics: Conference Series, 2019

Currently plate-type fuels are planned to use in the research reactor TRIGA-2000 Bandung, Indones... more Currently plate-type fuels are planned to use in the research reactor TRIGA-2000 Bandung, Indonesia (further called as TRIGA-Plate reactor). Plate type fuel consists of enriched uranium sandwiched between metal cladding. Plate-type fuel is used in some research reactors to obtain high neutron flux and is used to study material irradiation or isotope production. For the purpose of Safety Analysis Report (SAR) on the fuel-type modification plan of TRIGA-2000 Bandung, it is necessary to calculate radioactivity inventory from the reactor core under operating conditions. The radioactivity inventory of materials irradiated in a reactor depends on the initial material composition at the BOC, burn-up history from BOC to EOC and the power peaking factor. The purpose of the present work is to evaluate the fuel burn-up and radioactivity inventory in fuel materials of TRIGA-Plate research reactor. The mass of U-235 consumed and the mass of Pu-239 and Th-232 produced are also evaluated. The calculation results obtained using ORIGEN2 code are: the mass of U-235 consumed is 1.40E+02 gram; while the mass of Pu-239 produced is 1.36E+00 gram and Th-232 produced is 1.03E-06 gram. The largest radioactivity inventories of the reactor at the EOC sequentially are: Kr group is about 2.29E+02 Ci; for group I is 7.77E+03 Ci and for groups Cs is 1.92E+02Ci.