Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors
Neutron thermalization leads to the complexity of the scattering cross-section calculation, which influences the accuracy of the neutron transport calculation in the thermal energy range. The higher precision of thermal scattering data is demanded in the small modular reactors (SMRs) design, especia...
| Main Authors: | , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
MDPI AG
2023-04-01
|
| Series: | Journal of Nuclear Engineering |
| Subjects: | |
| Online Access: | https://www.mdpi.com/2673-4362/4/2/23 |
| _version_ | 1797594022532874240 |
|---|---|
| author | Jun Wu Yixue Chen |
| author_facet | Jun Wu Yixue Chen |
| author_sort | Jun Wu |
| collection | DOAJ |
| description | Neutron thermalization leads to the complexity of the scattering cross-section calculation, which influences the accuracy of the neutron transport calculation in the thermal energy range. The higher precision of thermal scattering data is demanded in the small modular reactors (SMRs) design, especially for small-sized PWRs and SCWRs. Additionally, the thermal neutron scattering problems in supercritical water have not yet been solved. In this study, the thermal neutron scattering problems in subcritical water are tested. Based on thermal neutron scattering theory, the GA model and IKE model were analyzed. This work selected the corresponding input parameters, such as the frequency spectrum, the discrete oscillator energy, weight parameters and so on, as well as preliminary studies on how to calculate the thermal scattering data for HinH<sub>2</sub>O to accomplish the calculation at various temperatures by developing LIPER code. The deviation between the calculated and reference results, which were both obtained by the Monte Carlo code, COSRMC, was below 0.2 pcm. The deviation of the scattering cross-section between the calculation results and reference was below 0.1%, indicating the reasonability of this study’s thermal scattering data calculation. |
| first_indexed | 2024-03-11T02:16:44Z |
| format | Article |
| id | doaj.art-c655aef203b9493a9b77153a3e52b22f |
| institution | Directory Open Access Journal |
| issn | 2673-4362 |
| language | English |
| last_indexed | 2024-03-11T02:16:44Z |
| publishDate | 2023-04-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Journal of Nuclear Engineering |
| spelling | doaj.art-c655aef203b9493a9b77153a3e52b22f2023-11-18T11:08:01ZengMDPI AGJournal of Nuclear Engineering2673-43622023-04-014230931610.3390/jne4020023Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular ReactorsJun Wu0Yixue Chen1School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaNeutron thermalization leads to the complexity of the scattering cross-section calculation, which influences the accuracy of the neutron transport calculation in the thermal energy range. The higher precision of thermal scattering data is demanded in the small modular reactors (SMRs) design, especially for small-sized PWRs and SCWRs. Additionally, the thermal neutron scattering problems in supercritical water have not yet been solved. In this study, the thermal neutron scattering problems in subcritical water are tested. Based on thermal neutron scattering theory, the GA model and IKE model were analyzed. This work selected the corresponding input parameters, such as the frequency spectrum, the discrete oscillator energy, weight parameters and so on, as well as preliminary studies on how to calculate the thermal scattering data for HinH<sub>2</sub>O to accomplish the calculation at various temperatures by developing LIPER code. The deviation between the calculated and reference results, which were both obtained by the Monte Carlo code, COSRMC, was below 0.2 pcm. The deviation of the scattering cross-section between the calculation results and reference was below 0.1%, indicating the reasonability of this study’s thermal scattering data calculation.https://www.mdpi.com/2673-4362/4/2/23small modular reactorscattering kernel modelthermal scattering dataHinH<sub>2</sub>O |
| spellingShingle | Jun Wu Yixue Chen Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors Journal of Nuclear Engineering small modular reactor scattering kernel model thermal scattering data HinH<sub>2</sub>O |
| title | Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors |
| title_full | Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors |
| title_fullStr | Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors |
| title_full_unstemmed | Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors |
| title_short | Preliminary Study on the Thermal Neutron Scattering Cross-Section for HinH<sub>2</sub>O in Small Modular Reactors |
| title_sort | preliminary study on the thermal neutron scattering cross section for hinh sub 2 sub o in small modular reactors |
| topic | small modular reactor scattering kernel model thermal scattering data HinH<sub>2</sub>O |
| url | https://www.mdpi.com/2673-4362/4/2/23 |
| work_keys_str_mv | AT junwu preliminarystudyonthethermalneutronscatteringcrosssectionforhinhsub2suboinsmallmodularreactors AT yixuechen preliminarystudyonthethermalneutronscatteringcrosssectionforhinhsub2suboinsmallmodularreactors |