REA 3D-dynamic analysis in Almaraz NPP with RELAP5/PARCS v2.7 and SIMTAB cross-sections tables

[EN] The Rod Ejection Accident (REA) belongs to the Reactivity-Initiated Accidents (RIA) category of accidents and it is part of the licensing basis accident analyses required for pressurized water reactors (PWR). The REA at Hot Zero Power (HZP) is characterized by a single rod ejection from a core...

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Detalles Bibliográficos
Autores: Barrachina, Teresa|||0000-0001-8794-4204, Miró Herrero, Rafael|||0000-0003-1012-0869, Verdú Martín, Gumersindo Jesús|||0000-0001-5098-080X, Garcia-Fenoll, Marina, Ánchel Añó, Francisco Constantino, Pereira, C., da Silva, C, Ortego, A., Martínez-Murillo, J.C
Tipo de recurso: artículo
Fecha de publicación:2011
País:España
Institución:Universitat Politècnica de València (UPV)
Repositorio:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
Idioma:inglés
OAI Identifier:oai:riunet.upv.es:10251/37873
Acceso en línea:https://riunet.upv.es/handle/10251/37873
Access Level:acceso abierto
Palabra clave:RIA analysis
Coupled codes
RELAP5
PARCSv2.7
Fuel enthalpy
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
Descripción
Sumario:[EN] The Rod Ejection Accident (REA) belongs to the Reactivity-Initiated Accidents (RIA) category of accidents and it is part of the licensing basis accident analyses required for pressurized water reactors (PWR). The REA at Hot Zero Power (HZP) is characterized by a single rod ejection from a core position with a very low power level. The evolution consists basically of a continuous reactivity insertion. The main feature limiting the consequences of the accident in a PWR is the Doppler Effect. To check the performance of the coupled code RELAP5/PARCS v2.7 a REA in Almaraz NPP is simulated. These analyses will allow knowing more accurately the PWR real plant phenomenology in the RIA most limiting conditions.

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