Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code
Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluat...
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| Format: | Article |
| Language: | English |
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Elsevier
2023-05-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323000086 |
| _version_ | 1797823786089709568 |
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| author | Surian Pinem Wahid Luthfi Peng Hong Liem Donny Hartanto |
| author_facet | Surian Pinem Wahid Luthfi Peng Hong Liem Donny Hartanto |
| author_sort | Surian Pinem |
| collection | DOAJ |
| description | Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity. |
| first_indexed | 2024-03-13T10:29:07Z |
| format | Article |
| id | doaj.art-a2797f97663f48a4aec1ed4291f0d376 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-13T10:29:07Z |
| publishDate | 2023-05-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-a2797f97663f48a4aec1ed4291f0d3762023-05-19T04:45:11ZengElsevierNuclear Engineering and Technology1738-57332023-05-0155517751782Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo codeSurian Pinem0Wahid Luthfi1Peng Hong Liem2Donny Hartanto3Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency (BRIN), 80th Building of PUSPIPTEK Serpong, South Tangerang, Banten, Indonesia; Corresponding author.Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency (BRIN), 80th Building of PUSPIPTEK Serpong, South Tangerang, Banten, IndonesiaCooperative Major in Nuclear Energy, Graduate School of Engineering, Tokyo City University (TCU), 1-28-1, Tamazutsumi, Setagaya, Tokyo, Japan; Scientific Computational Division, Nippon Advanced Information Service, (NAIS Co., Inc.), 416 Muramatsu, Tokaimura, Ibaraki, JapanOak Ridge National Laboratory One Bethel Valley Road, Oak Ridge, TN, 37830, USASeveral reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity.http://www.sciencedirect.com/science/article/pii/S1738573323000086Neutronic parameterControl rod worthFuel element reactivityRSG-GASSerpent 2 |
| spellingShingle | Surian Pinem Wahid Luthfi Peng Hong Liem Donny Hartanto Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code Nuclear Engineering and Technology Neutronic parameter Control rod worth Fuel element reactivity RSG-GAS Serpent 2 |
| title | Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code |
| title_full | Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code |
| title_fullStr | Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code |
| title_full_unstemmed | Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code |
| title_short | Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code |
| title_sort | evaluation of neutronics parameters during rsg gas commissioning by using monte carlo code |
| topic | Neutronic parameter Control rod worth Fuel element reactivity RSG-GAS Serpent 2 |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323000086 |
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