Testing thermal scattering law for light ...
Type de document :
Autre communication scientifique (congrès sans actes - poster - séminaire...): Communication dans un congrès avec actes
Titre :
Testing thermal scattering law for light water at 600 k using vesta 2.2.0 depletion calculations
Auteur(s) :
Raphaëlle, Ichou [Auteur]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Jaiswal, Vaibhav [Auteur]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Leal, Luiz [Auteur]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Réal, Florent [Auteur]
Physico-Chimie Moléculaire Théorique [PCMT]
Vallet, Valérie [Auteur]
Physico-Chimie Moléculaire Théorique [PCMT]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Jaiswal, Vaibhav [Auteur]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Leal, Luiz [Auteur]
Laboratoire de Neutronique [IRSN/PSN-EXP/SNC/LN]
Réal, Florent [Auteur]
Physico-Chimie Moléculaire Théorique [PCMT]
Vallet, Valérie [Auteur]
Physico-Chimie Moléculaire Théorique [PCMT]
Titre de la manifestation scientifique :
11th International conference on Nuclear Criticality Safety, ICNC 2019
Ville :
PARIS
Pays :
France
Date de début de la manifestation scientifique :
2019-09-15
Date de publication :
2019
Discipline(s) HAL :
Sciences de l'ingénieur [physics]
Résumé en anglais : [en]
Recent releases of the US and European evaluated nuclear data libraries, namely ENDF/B-VIII.0 and JEFF-3.3, included H2O reviewed versions of thermal scattering law (TSL) data. TheENDF/B-VIII.0 adopted evaluation is based ...
Lire la suite >Recent releases of the US and European evaluated nuclear data libraries, namely ENDF/B-VIII.0 and JEFF-3.3, included H2O reviewed versions of thermal scattering law (TSL) data. TheENDF/B-VIII.0 adopted evaluation is based on molecular dynamics (MD) simulations whereas JEFF data are based on experimental measurements. While the ENDF and JEFF evaluations perform decently well for room temperature, performance for temperatures other than room temperature is needed. At IRSN, an effort has been devoted to the investigation and evaluation of H(H2O) TSL for temperatures higher than room temperature for reactor safety and criticality safety applications. For so, thermal neutron scattering cross section for hydrogen bound in light water was re-evaluated at reactor operating temperature, i.e., at 600 K based on MD simulations using the PolarisMD code and TCPE polarizable rigid water model potential. In this work, we present the impact of this new IRSN TSL data for light water for PWR using VESTA 2.2.0 depletion calculations, by comparing the results obtained using both ENDF/B-VIII.0 and the new TSL data. The VESTA 2.2.0 calculations are performed for the ARIANE.GU3 sample, which is a PWR UO2 fuel rod sample with an estimated burn up of 52.5 MWd.kgHM-1, irradiated in the Gösgen PWR in Switzerland between 1994 and 1997 during three cycles. The results are compared to the ones obtained with previous thermal scattering cross sections for light water from the JEFF evaluations. For validation purpose, they are also compared to experimental dataLire moins >
Lire la suite >Recent releases of the US and European evaluated nuclear data libraries, namely ENDF/B-VIII.0 and JEFF-3.3, included H2O reviewed versions of thermal scattering law (TSL) data. TheENDF/B-VIII.0 adopted evaluation is based on molecular dynamics (MD) simulations whereas JEFF data are based on experimental measurements. While the ENDF and JEFF evaluations perform decently well for room temperature, performance for temperatures other than room temperature is needed. At IRSN, an effort has been devoted to the investigation and evaluation of H(H2O) TSL for temperatures higher than room temperature for reactor safety and criticality safety applications. For so, thermal neutron scattering cross section for hydrogen bound in light water was re-evaluated at reactor operating temperature, i.e., at 600 K based on MD simulations using the PolarisMD code and TCPE polarizable rigid water model potential. In this work, we present the impact of this new IRSN TSL data for light water for PWR using VESTA 2.2.0 depletion calculations, by comparing the results obtained using both ENDF/B-VIII.0 and the new TSL data. The VESTA 2.2.0 calculations are performed for the ARIANE.GU3 sample, which is a PWR UO2 fuel rod sample with an estimated burn up of 52.5 MWd.kgHM-1, irradiated in the Gösgen PWR in Switzerland between 1994 and 1997 during three cycles. The results are compared to the ones obtained with previous thermal scattering cross sections for light water from the JEFF evaluations. For validation purpose, they are also compared to experimental dataLire moins >
Langue :
Anglais
Comité de lecture :
Non
Audience :
Internationale
Vulgarisation :
Non
Source :
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