VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS
The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid Metal Cooled Fast reactor (LMFR). These develop...
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| Format: | Article |
| Language: | English |
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EDP Sciences
2021-01-01
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| Series: | EPJ Web of Conferences |
| Subjects: | |
| Online Access: | https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_03020.pdf |
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| author | Smith Peter Hosking Glynn Tollit Brendan Lindley Ben Cox Andrew Perry Ray Ware Tim Mason Robert Stefanowska Magda |
| author_facet | Smith Peter Hosking Glynn Tollit Brendan Lindley Ben Cox Andrew Perry Ray Ware Tim Mason Robert Stefanowska Magda |
| author_sort | Smith Peter |
| collection | DOAJ |
| description | The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid Metal Cooled Fast reactor (LMFR). These developments include the capability for whole core multiphysics modelling with neutronics and thermal hydraulic feedback, as well as methods to determine the power deposition from neutron and gamma heating. Flux solutions are obtained using a wide variety of deterministic methods including diffusion theory, SP3, and full transport with the method of characteristics and Sn discrete ordinates methods, as well as multi-group Monte Carlo methods. The SP3 method allows both steady state and time dependent transient solutions by solving the time dependent SP3 equations. A wide variety of nuclear data libraries are available with WIMS including data from the JEF3.3, ENDF/B-VII.0 and CENDL3.1 nuclear data evaluations.
This paper presents validation of the latest version of the WIMS code, WIMS11, for PWR and HTR systems. Comparisons are made against physics data obtained from the OECD/NEA PWR Watts Bar multi-physics benchmark and the IAEA HTR-10 benchmark, as well as neutron and gamma heating experiments that took place on the NESSUS reactor at Winfrith in the United Kingdom. In each case, validation of WIMS has been obtained by comparison either against measured data, or results provided by other benchmark participants that have been obtained with alternative deterministic or Monte Carlo methods. |
| first_indexed | 2024-12-13T19:21:50Z |
| format | Article |
| id | doaj.art-2a662cbe32e44f0cbd918361450daad3 |
| institution | Directory Open Access Journal |
| issn | 2100-014X |
| language | English |
| last_indexed | 2024-12-13T19:21:50Z |
| publishDate | 2021-01-01 |
| publisher | EDP Sciences |
| record_format | Article |
| series | EPJ Web of Conferences |
| spelling | doaj.art-2a662cbe32e44f0cbd918361450daad32022-12-21T23:34:08ZengEDP SciencesEPJ Web of Conferences2100-014X2021-01-012470302010.1051/epjconf/202124703020epjconf_physor2020_03020VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSISSmith Peter0Hosking Glynn1Tollit Brendan2Lindley Ben3Cox Andrew4Perry Ray5Ware Tim6Mason Robert7Stefanowska Magda8Wood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareWood Nuclear Queen Mother SquareThe WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid Metal Cooled Fast reactor (LMFR). These developments include the capability for whole core multiphysics modelling with neutronics and thermal hydraulic feedback, as well as methods to determine the power deposition from neutron and gamma heating. Flux solutions are obtained using a wide variety of deterministic methods including diffusion theory, SP3, and full transport with the method of characteristics and Sn discrete ordinates methods, as well as multi-group Monte Carlo methods. The SP3 method allows both steady state and time dependent transient solutions by solving the time dependent SP3 equations. A wide variety of nuclear data libraries are available with WIMS including data from the JEF3.3, ENDF/B-VII.0 and CENDL3.1 nuclear data evaluations. This paper presents validation of the latest version of the WIMS code, WIMS11, for PWR and HTR systems. Comparisons are made against physics data obtained from the OECD/NEA PWR Watts Bar multi-physics benchmark and the IAEA HTR-10 benchmark, as well as neutron and gamma heating experiments that took place on the NESSUS reactor at Winfrith in the United Kingdom. In each case, validation of WIMS has been obtained by comparison either against measured data, or results provided by other benchmark participants that have been obtained with alternative deterministic or Monte Carlo methods.https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_03020.pdfwimsvalidationpwrhtrheating |
| spellingShingle | Smith Peter Hosking Glynn Tollit Brendan Lindley Ben Cox Andrew Perry Ray Ware Tim Mason Robert Stefanowska Magda VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS EPJ Web of Conferences wims validation pwr htr heating |
| title | VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS |
| title_full | VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS |
| title_fullStr | VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS |
| title_full_unstemmed | VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS |
| title_short | VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS |
| title_sort | validation of wims11 for small modular reactor analysis |
| topic | wims validation pwr htr heating |
| url | https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_03020.pdf |
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