Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis

Álvarez Velarde, F.; González Romero, E.M. y Merino Rodríguez, Iván (2014). Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis. "Annals of Nuclear Energy", v. 73 (n. null); pp. 175-188. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2014.06.049.

Descripción

Título: Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis
Autor/es:
  • Álvarez Velarde, F.
  • González Romero, E.M.
  • Merino Rodríguez, Iván
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: 2014
Volumen: 73
Materias:
Palabras Clave Informales: Burn-up code, Code validation, Sensitivity/Uncertainty analysis, Uncertainty propagation
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Otro
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

A validation of the burn-up simulation system EVOLCODE 2.0 is presented here, involving the experimental measurement of U and Pu isotopes and some fission fragments production ratios after a burn-up of around 30 GWd/tU in a Pressurized Light Water Reactor (PWR). This work provides an in-depth analysis of the validation results, including the possible sources of the uncertainties. An uncertainty analysis based on the sensitivity methodology has been also performed, providing the uncertainties in the isotopic content propagated from the cross sections uncertainties. An improvement of the classical Sensitivity/ Uncertainty (S/U) model has been developed to take into account the implicit dependence of the neutron flux normalization, that is, the effect of the constant power of the reactor. The improved S/U methodology, neglected in this kind of studies, has proven to be an important contribution to the explanation of some simulation-experiment discrepancies for which, in general, the cross section uncertainties are, for the most relevant actinides, an important contributor to the simulation uncertainties, of the same order of magnitude and sometimes even larger than the experimental uncertainties and the experiment- simulation differences. Additionally, some hints for the improvement of the JEFF3.1.1 fission yield library and for the correction of some errata in the experimental data are presented.

Proyectos asociados

TipoCódigoAcrónimoResponsableTítulo
FP7249671ANDES (Accurate Nuclear data for Nuclear Energy Sustainability)Sin especificarANDES (Accurate Nuclear data for Nuclear Energy Sustainability)

Más información

ID de Registro: 33091
Identificador DC: http://oa.upm.es/33091/
Identificador OAI: oai:oa.upm.es:33091
Identificador DOI: 10.1016/j.anucene.2014.06.049
URL Oficial: http://www.sciencedirect.com/science/article/pii/S0306454914003120
Depositado por: Memoria Investigacion
Depositado el: 12 Dic 2014 19:21
Ultima Modificación: 19 Dic 2014 17:32
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