Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors

Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by re...

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Detalles Bibliográficos
Autores: Deen, James R., Lázaro, Gerardo, Woodruff, William L.
Tipo de recurso: artículo
Fecha de publicación:2002
País:Perú
Institución:Instituto Peruano de Energía Nuclear
Repositorio:IPEN-Institucional
Idioma:inglés
OAI Identifier:oai:repositorio.ipen.gob.pe:20.500.13054/168
Acceso en línea:https://hdl.handle.net/20.500.13054/168
Access Level:acceso abierto
Palabra clave:Reactor RP-10
Reactor RP-0
Análisis de seguridad
Cálculos por ordenadores
Método de Monte Carlo
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spelling Deen, James R.Lázaro, GerardoWoodruff, William L.Lázaro, GerardoDeen, James R.Woodruff, William L.2014-06-02T19:07:00Z2014-06-02T19:07:00Z2002-06Lázaro G, Deen JR, Woodruff WL. Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors. Instituto Peruano de Energía Nuclear. Informe Científico Tecnológico. 1998-2001;:6-10.1684-1662https://hdl.handle.net/20.500.13054/168Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by reactivity insertion accidents. It was done to show the trend of these reactivity coefficients as a function of the core size and fuel depletion for RP10 cores. It was useful to get a better understanding of the progression of the reactivity insertion transients monitoring the critical thermal hydraulic parameters to avoid core damage. To confirm the accuracy of these studies the results were compared with experimental data of the SPERT I reactors. The microscopic cross section calculations were condensed to 15 broad groups using the WIMSD4M[1] code for all the isotopes from eight different regions that model seven different assemblies. The Supercell, multiplate and homogenized options were used to represent the different assemblies in the reactor. For diffusion theory calculations the DIF3D[2] code was used in planar geometry with input axial buckling to simulate axial leakage. To Benchmark the designed models used in the cross sections generation and the DIF3D designed model, the VIM[3] Monte Carlo code was used. The RECOEFF[4] code was used to calculate the reactivity coefficients.Instituto Peruano de Energía Nuclearapplication/pdfengLimaPEinfo:eu-repo/semantics/openAccessInstituto Peruano de Energía NuclearRepositorio Institucional del Instituto Peruano de Energía Nuclearreponame:IPEN-Institucionalinstname:Instituto Peruano de Energía Nuclearinstacron:IPENReactor RP-10Reactor RP-0Análisis de seguridadCálculos por ordenadoresMétodo de Monte CarloNeutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactorsCálculo neutrónico de parámetros de seguridad de los reactores RP-10 y RP-0info:eu-repo/semantics/articleORIGINALPag. 6-10 - ICT 1998-2001.pdfPag. 6-10 - ICT 1998-2001.pdfapplication/pdf155969https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/1/Pag.%206-10%20-%20ICT%201998-2001.pdf7e28d3764da1dcc1f025f606b4d7ae70MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-8103https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/2/license.txt7ecf7b0639239de61a3a1ede9c397fecMD52TEXTPag. 6-10 - ICT 1998-2001.pdf.txtPag. 6-10 - ICT 1998-2001.pdf.txtExtracted texttext/plain12516https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/3/Pag.%206-10%20-%20ICT%201998-2001.pdf.txt0e2410ebe1f4f9403eb6f4cd747bd0d4MD53THUMBNAILPag. 6-10 - ICT 1998-2001.pdf.jpgPag. 6-10 - ICT 1998-2001.pdf.jpgGenerated Thumbnailimage/jpeg19147https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/4/Pag.%206-10%20-%20ICT%201998-2001.pdf.jpgc9e65874d2dc8aa79d2533d3ef35b749MD5420.500.13054/168oai:repositorio.ipen.gob.pe:20.500.13054/1682022-02-07 18:05:08.03Repositorio Institucional del Instituto Peruano de Energía Nuclearrepositorio@ipen.gob.peU2UgRGlzdHJpYnV5ZSBiYWpvIHVuYSBMaWNlbmNpYSBDcmVhdGl2ZSBDb21tb25zIEF0cmlidWNpw7NuLU5vQ29tZXJjaWFsLVNpbkRlcml2YXIgNC4wIEludGVybmFjaW9uYWwuCg==
dc.title.es_PE.fl_str_mv Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
dc.title.alternative.es_PE.fl_str_mv Cálculo neutrónico de parámetros de seguridad de los reactores RP-10 y RP-0
title Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
spellingShingle Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
Deen, James R.
Reactor RP-10
Reactor RP-0
Análisis de seguridad
Cálculos por ordenadores
Método de Monte Carlo
title_short Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
title_full Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
title_fullStr Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
title_full_unstemmed Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
title_sort Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
dc.creator.none.fl_str_mv Deen, James R.
Lázaro, Gerardo
Woodruff, William L.
Lázaro, Gerardo
Deen, James R.
Woodruff, William L.
author Deen, James R.
author_facet Deen, James R.
Lázaro, Gerardo
Woodruff, William L.
author_role author
author2 Lázaro, Gerardo
Woodruff, William L.
author2_role author
author
dc.subject.es_PE.fl_str_mv Reactor RP-10
Reactor RP-0
Análisis de seguridad
Cálculos por ordenadores
Método de Monte Carlo
topic Reactor RP-10
Reactor RP-0
Análisis de seguridad
Cálculos por ordenadores
Método de Monte Carlo
description Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by reactivity insertion accidents. It was done to show the trend of these reactivity coefficients as a function of the core size and fuel depletion for RP10 cores. It was useful to get a better understanding of the progression of the reactivity insertion transients monitoring the critical thermal hydraulic parameters to avoid core damage. To confirm the accuracy of these studies the results were compared with experimental data of the SPERT I reactors. The microscopic cross section calculations were condensed to 15 broad groups using the WIMSD4M[1] code for all the isotopes from eight different regions that model seven different assemblies. The Supercell, multiplate and homogenized options were used to represent the different assemblies in the reactor. For diffusion theory calculations the DIF3D[2] code was used in planar geometry with input axial buckling to simulate axial leakage. To Benchmark the designed models used in the cross sections generation and the DIF3D designed model, the VIM[3] Monte Carlo code was used. The RECOEFF[4] code was used to calculate the reactivity coefficients.
publishDate 2002
dc.date.accessioned.none.fl_str_mv 2014-06-02T19:07:00Z
dc.date.available.none.fl_str_mv 2014-06-02T19:07:00Z
dc.date.issued.fl_str_mv 2002-06
dc.type.es_PE.fl_str_mv info:eu-repo/semantics/article
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dc.identifier.citation.es_PE.fl_str_mv Lázaro G, Deen JR, Woodruff WL. Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors. Instituto Peruano de Energía Nuclear. Informe Científico Tecnológico. 1998-2001;:6-10.
dc.identifier.issn.none.fl_str_mv 1684-1662
dc.identifier.uri.none.fl_str_mv https://hdl.handle.net/20.500.13054/168
identifier_str_mv Lázaro G, Deen JR, Woodruff WL. Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors. Instituto Peruano de Energía Nuclear. Informe Científico Tecnológico. 1998-2001;:6-10.
1684-1662
url https://hdl.handle.net/20.500.13054/168
dc.language.iso.es_PE.fl_str_mv eng
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dc.source.es_PE.fl_str_mv Instituto Peruano de Energía Nuclear
Repositorio Institucional del Instituto Peruano de Energía Nuclear
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instname_str Instituto Peruano de Energía Nuclear
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