FSAR: Full neutron spectrum code for advanced reactor simulation
The full neutron spectrum code for advanced reactor simulation named FSAR has recently been developed at Nuclear Power Institute of China in order to meet the requirements of advanced reactor with large neutron energy range. Based on the two-step calculation scheme, FSAR consists of two-dimensional...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Frontiers Media S.A.
2023-02-01
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| Series: | Frontiers in Energy Research |
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| Online Access: | https://www.frontiersin.org/articles/10.3389/fenrg.2023.1123714/full |
| _version_ | 1811168196592402432 |
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| author | Lianjie Wang Bin Zhang Di Lu Chen Zhao Jiayi Liu |
| author_facet | Lianjie Wang Bin Zhang Di Lu Chen Zhao Jiayi Liu |
| author_sort | Lianjie Wang |
| collection | DOAJ |
| description | The full neutron spectrum code for advanced reactor simulation named FSAR has recently been developed at Nuclear Power Institute of China in order to meet the requirements of advanced reactor with large neutron energy range. Based on the two-step calculation scheme, FSAR consists of two-dimensional lattice calculation code and core calculation code. In two-dimensional lattice calculation, the subgroup method with ultrafine energy groups was implemented in the two-dimensional resonance self-shielding by incorporating the MOC to get the accurate self-shielded cross-section. For better consideration of the strong space coupling in different geometric sizes due to different mean free path of neutrons, the super-homogenization method and the leakage model were applied. In the core calculation, the discrete-ordinate method and micro burnup calculation method were used to simulate the core neutron transport and depletion. Preliminary calculation results showed that for the problems with wide spectrum, the self-shielded cross-sections have a good agreement with the Monte Carlo solution. The results shown in this paper indicate that FSAR has good performances of the cross-section generation in full neutron spectrum problem simulation. |
| first_indexed | 2024-04-10T16:23:09Z |
| format | Article |
| id | doaj.art-1103f528838746f39cc2d7334a48a2e4 |
| institution | Directory Open Access Journal |
| issn | 2296-598X |
| language | English |
| last_indexed | 2024-04-10T16:23:09Z |
| publishDate | 2023-02-01 |
| publisher | Frontiers Media S.A. |
| record_format | Article |
| series | Frontiers in Energy Research |
| spelling | doaj.art-1103f528838746f39cc2d7334a48a2e42023-02-09T10:18:15ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2023-02-011110.3389/fenrg.2023.11237141123714FSAR: Full neutron spectrum code for advanced reactor simulationLianjie WangBin ZhangDi LuChen ZhaoJiayi LiuThe full neutron spectrum code for advanced reactor simulation named FSAR has recently been developed at Nuclear Power Institute of China in order to meet the requirements of advanced reactor with large neutron energy range. Based on the two-step calculation scheme, FSAR consists of two-dimensional lattice calculation code and core calculation code. In two-dimensional lattice calculation, the subgroup method with ultrafine energy groups was implemented in the two-dimensional resonance self-shielding by incorporating the MOC to get the accurate self-shielded cross-section. For better consideration of the strong space coupling in different geometric sizes due to different mean free path of neutrons, the super-homogenization method and the leakage model were applied. In the core calculation, the discrete-ordinate method and micro burnup calculation method were used to simulate the core neutron transport and depletion. Preliminary calculation results showed that for the problems with wide spectrum, the self-shielded cross-sections have a good agreement with the Monte Carlo solution. The results shown in this paper indicate that FSAR has good performances of the cross-section generation in full neutron spectrum problem simulation.https://www.frontiersin.org/articles/10.3389/fenrg.2023.1123714/fullfull neutron spectrumadvanced reactortwo-dimensional lattice calculationself-shielded cross-sectioncore simulation |
| spellingShingle | Lianjie Wang Bin Zhang Di Lu Chen Zhao Jiayi Liu FSAR: Full neutron spectrum code for advanced reactor simulation Frontiers in Energy Research full neutron spectrum advanced reactor two-dimensional lattice calculation self-shielded cross-section core simulation |
| title | FSAR: Full neutron spectrum code for advanced reactor simulation |
| title_full | FSAR: Full neutron spectrum code for advanced reactor simulation |
| title_fullStr | FSAR: Full neutron spectrum code for advanced reactor simulation |
| title_full_unstemmed | FSAR: Full neutron spectrum code for advanced reactor simulation |
| title_short | FSAR: Full neutron spectrum code for advanced reactor simulation |
| title_sort | fsar full neutron spectrum code for advanced reactor simulation |
| topic | full neutron spectrum advanced reactor two-dimensional lattice calculation self-shielded cross-section core simulation |
| url | https://www.frontiersin.org/articles/10.3389/fenrg.2023.1123714/full |
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