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Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient

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Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient

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Garcia-Fenoll, M.; Mesado Melia, C.; Barrachina, T.; Miró Herrero, R.; Verdú Martín, GJ.; Bermejo, JA.; López, A.... (2017). Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient. Journal of Nuclear Science and Technology. 54(8):908-919. https://doi.org/10.1080/00223131.2017.1329035

Por favor, use este identificador para citar o enlazar este ítem: http://hdl.handle.net/10251/101859

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Title: Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient
Author: Garcia-Fenoll, Marina Mesado Melia, Carles Barrachina, T. Miró Herrero, Rafael Verdú Martín, Gumersindo Jesús Bermejo, Juan Antonio López, Arturo Ortego, Alberto
UPV Unit: Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear
Universitat Politècnica de València. Instituto de Seguridad Industrial, Radiofísica y Medioambiental - Institut de Seguretat Industrial, Radiofísica i Mediambiental
Issued date:
Abstract:
[EN] In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue. New capabilities implementation, as well as models and tools improvements are a significant part of the community effort ...[+]
Subjects: PWR type reactor , RIA , Control rod , RELAP5/mod3.3 , TRACEv5.0P3 , PARCS
Copyrigths: Reserva de todos los derechos
Source:
Journal of Nuclear Science and Technology. (issn: 0022-3131 )
DOI: 10.1080/00223131.2017.1329035
Publisher:
Taylor & Francis
Publisher version: https://doi.org/10.1080/00223131.2017.1329035
Project ID:
MINECO/ENE2012-34585
MINECO/ENE2011-22823
GV/PROMETEOII/2014/008
Thanks:
The authors would like to acknowledge the economic support provided by Centrales Nucleares Almaraz-Trillo (CNAT) and IBERDROLA Ingeniería y Construcción (Iberinco) for the realization of this work, and express their great ...[+]
Type: Artículo

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