Macroscopic cross section generation with WIMS-ANL for a PWR
Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels ass...
Ausführliche Beschreibung
Autor*in: |
Wilmer Aruquipa Coloma [verfasserIn] Patrícia Amélia de Lima Reis [verfasserIn] Clarysson Alberto Mello da Silva [verfasserIn] Claubia Pereira Bezerra Lima [verfasserIn] |
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Format: |
E-Artikel |
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Sprache: |
Englisch ; Portugiesisch |
Erschienen: |
2022 |
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Schlagwörter: |
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Übergeordnetes Werk: |
In: Brazilian Journal of Radiation Sciences - Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022, 10(2022), 3A |
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Übergeordnetes Werk: |
volume:10 ; year:2022 ; number:3A |
Links: |
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DOI / URN: |
10.15392/2319-0612.2022.1948 |
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Katalog-ID: |
DOAJ079629180 |
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10.15392/2319-0612.2022.1948 doi (DE-627)DOAJ079629180 (DE-599)DOAJ18026447fa154e11a0e1a29f57786dc4 DE-627 ger DE-627 rakwb eng por Wilmer Aruquipa Coloma verfasserin aut Macroscopic cross section generation with WIMS-ANL for a PWR 2022 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. Macroscopic cross sections BEAVRS PWR Science Q Patrícia Amélia de Lima Reis verfasserin aut Clarysson Alberto Mello da Silva verfasserin aut Claubia Pereira Bezerra Lima verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 10(2022), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:10 year:2022 number:3A https://doi.org/10.15392/2319-0612.2022.1948 kostenfrei https://doaj.org/article/18026447fa154e11a0e1a29f57786dc4 kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1948 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 10 2022 3A |
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10.15392/2319-0612.2022.1948 doi (DE-627)DOAJ079629180 (DE-599)DOAJ18026447fa154e11a0e1a29f57786dc4 DE-627 ger DE-627 rakwb eng por Wilmer Aruquipa Coloma verfasserin aut Macroscopic cross section generation with WIMS-ANL for a PWR 2022 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. Macroscopic cross sections BEAVRS PWR Science Q Patrícia Amélia de Lima Reis verfasserin aut Clarysson Alberto Mello da Silva verfasserin aut Claubia Pereira Bezerra Lima verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 10(2022), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:10 year:2022 number:3A https://doi.org/10.15392/2319-0612.2022.1948 kostenfrei https://doaj.org/article/18026447fa154e11a0e1a29f57786dc4 kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1948 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 10 2022 3A |
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10.15392/2319-0612.2022.1948 doi (DE-627)DOAJ079629180 (DE-599)DOAJ18026447fa154e11a0e1a29f57786dc4 DE-627 ger DE-627 rakwb eng por Wilmer Aruquipa Coloma verfasserin aut Macroscopic cross section generation with WIMS-ANL for a PWR 2022 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. Macroscopic cross sections BEAVRS PWR Science Q Patrícia Amélia de Lima Reis verfasserin aut Clarysson Alberto Mello da Silva verfasserin aut Claubia Pereira Bezerra Lima verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 10(2022), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:10 year:2022 number:3A https://doi.org/10.15392/2319-0612.2022.1948 kostenfrei https://doaj.org/article/18026447fa154e11a0e1a29f57786dc4 kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1948 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 10 2022 3A |
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Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. |
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Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. |
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Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation. |
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