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

Álvarez Velarde, F. and González Romero, E.M. and 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.

Description

Title: Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis
Author/s:
  • Álvarez Velarde, F.
  • González Romero, E.M.
  • Merino Rodríguez, Iván
Item Type: Article
Título de Revista/Publicación: Annals of Nuclear Energy
Date: 2014
ISSN: 0306-4549
Volume: 73
Subjects:
Freetext Keywords: Burn-up code, Code validation, Sensitivity/Uncertainty analysis, Uncertainty propagation
Faculty: E.T.S.I. Industriales (UPM)
Department: Otro
Creative Commons Licenses: Recognition - No derivative works - Non commercial

Full text

[img]
Preview
PDF - Requires a PDF viewer, such as GSview, Xpdf or Adobe Acrobat Reader
Download (4MB) | Preview

Abstract

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.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7249671ANDESCentro de Investigaciones Energéticas, Mediambientales y TecnológicasAccurate Nuclear Data for nuclear Energy Sustainability

More information

Item ID: 33091
DC Identifier: http://oa.upm.es/33091/
OAI Identifier: oai:oa.upm.es:33091
DOI: 10.1016/j.anucene.2014.06.049
Official URL: http://www.sciencedirect.com/science/article/pii/S0306454914003120
Deposited by: Memoria Investigacion
Deposited on: 12 Dec 2014 19:21
Last Modified: 14 May 2019 12:36
  • Logo InvestigaM (UPM)
  • Logo GEOUP4
  • Logo Open Access
  • Open Access
  • Logo Sherpa/Romeo
    Check whether the anglo-saxon journal in which you have published an article allows you to also publish it under open access.
  • Logo Dulcinea
    Check whether the spanish journal in which you have published an article allows you to also publish it under open access.
  • Logo de Recolecta
  • Logo del Observatorio I+D+i UPM
  • Logo de OpenCourseWare UPM