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...
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Autor*in:	Wilmer Aruquipa Coloma [verfasserIn] Patrícia Amélia de Lima Reis [verfasserIn] Clarysson Alberto Mello da Silva [verfasserIn] Claubia Pereira Bezerra Lima [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch ; Portugiesisch

Erschienen:	2022

Schlagwörter:	Macroscopic cross sections BEAVRS PWR

Übergeordnetes Werk:	In: Brazilian Journal of Radiation Sciences - Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022, 10(2022), 3A
Übergeordnetes Werk:	volume:10 ; year:2022 ; number:3A

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.15392/2319-0612.2022.1948

Katalog-ID:	DOAJ079629180

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language	English Portuguese
source	In Brazilian Journal of Radiation Sciences 10(2022), 3A volume:10 year:2022 number:3A
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authorswithroles_txt_mv	Wilmer Aruquipa Coloma @@aut@@ Patrícia Amélia de Lima Reis @@aut@@ Clarysson Alberto Mello da Silva @@aut@@ Claubia Pereira Bezerra Lima @@aut@@
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author	Wilmer Aruquipa Coloma
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topic_title	Macroscopic cross section generation with WIMS-ANL for a PWR Macroscopic cross sections BEAVRS PWR
topic	misc Macroscopic cross sections misc BEAVRS misc PWR misc Science misc Q
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title	Macroscopic cross section generation with WIMS-ANL for a PWR
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title_sort	macroscopic cross section generation with wims-anl for a pwr
title_auth	Macroscopic cross section generation with WIMS-ANL for a PWR
abstract	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.
abstractGer	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.
abstract_unstemmed	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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title_short	Macroscopic cross section generation with WIMS-ANL for a PWR
url	https://doi.org/10.15392/2319-0612.2022.1948 https://doaj.org/article/18026447fa154e11a0e1a29f57786dc4 https://bjrs.org.br/revista/index.php/REVISTA/article/view/1948 https://doaj.org/toc/2319-0612
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Macroscopic cross section generation with WIMS-ANL for a PWR

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