Development of a PWR-W and an AP1000® containment building 3D model with a CFD code for Best-Estimate Thermal-Hydraulic Analysis

Jiménez Varas, Gonzalo ORCID: https://orcid.org/0000-0003-2710-3029, Bocanegra, Rafael, Fernández, Kevin, Queral Salazar, José Cesar ORCID: https://orcid.org/0000-0001-9384-2474 and Montero-Mayorga, Javier (2014). Development of a PWR-W and an AP1000® containment building 3D model with a CFD code for Best-Estimate Thermal-Hydraulic Analysis. En: "22nd International Conference on Nuclear Engineering (ICONE22)", July 7-11, 2014, Prague, Czech Republic. ISBN 978-0-7918-4594-3. pp. 9-16.

Descripción

Título: Development of a PWR-W and an AP1000® containment building 3D model with a CFD code for Best-Estimate Thermal-Hydraulic Analysis
Autor/es:
Tipo de Documento: Ponencia en Congreso o Jornada (Artículo)
Título del Evento: 22nd International Conference on Nuclear Engineering (ICONE22)
Fechas del Evento: July 7-11, 2014
Lugar del Evento: Prague, Czech Republic
Título del Libro: Proceedings of the 22nd International Conference on Nuclear Engineering ICONE22
Fecha: 2014
ISBN: 978-0-7918-4594-3
Volumen: 4
Materias:
ODS:
Palabras Clave Informales: Computational fluid dynamics, Three-dimensional models, Pressurized water reactors, Containment buildings
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Energética
Licencias Creative Commons: Ninguna

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Resumen

The simulation of design basis accidents in a containment building is usually conducted with a lumped parameter model. The codes normally used by Westinghouse Electric Company (WEC) for that license analysis are WGOTHIC or COCO, which are suitable to provide an adequate estimation of the overall peak temperature and pressure of the containment. However, for the detailed study of the thermal-hydraulic behavior in every room and compartment of the containment building, it could be more convenient to model the containment with a more detailed 3D representation of the geometry of the whole building.

The main objective of this project is to obtain a standard PWR Westinghouse as well as an AP1000® containment model for a CFD code to analyze the thermal-hydraulic detailed behavior during a design basis accident. In this paper the development and testing of both containment models is presented.

Proyectos asociados

Tipo
Código
Acrónimo
Responsable
Título
Gobierno de España
ENE2011-28256
ISAMAR
Sin especificar
Aplicación de la metodología de análisis integrado de la seguridad a reactores nucleares avanzados

Más información

ID de Registro: 36654
Identificador DC: https://oa.upm.es/36654/
Identificador OAI: oai:oa.upm.es:36654
URL Oficial: http://proceedings.asmedigitalcollection.asme.org/...
Depositado por: Memoria Investigacion
Depositado el: 09 Mar 2016 11:36
Ultima Modificación: 08 Abr 2019 17:35