Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

Rochman, Dimitri and Leray, O. and Hursin, M. and Ferroukhi, H. and Vasiliev, A. and Aures, A. and Bostelmann, F. and Zwermann, W. and Cabellos, O. and Díez, C. J. and Dyrda, J. and García Herranz, Nuria and Castro González, Emilio and Van der Marck, S. and Sjostrand, H. and Hernández, A. and Fleming, M. and Sublet, J. Ch. and Fiorito, Luca (2017). Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core. "Nuclear Data Sheets", v. 139 ; pp. 1-76. ISSN 0090-3752. https://doi.org/10.1016/j.nds.2017.01.001.

Description

Title: Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
Author/s:
  • Rochman, Dimitri
  • Leray, O.
  • Hursin, M.
  • Ferroukhi, H.
  • Vasiliev, A.
  • Aures, A.
  • Bostelmann, F.
  • Zwermann, W.
  • Cabellos, O.
  • Díez, C. J.
  • Dyrda, J.
  • García Herranz, Nuria
  • Castro González, Emilio
  • Van der Marck, S.
  • Sjostrand, H.
  • Hernández, A.
  • Fleming, M.
  • Sublet, J. Ch.
  • Fiorito, Luca
Item Type: Article
Título de Revista/Publicación: Nuclear Data Sheets
Date: January 2017
ISSN: 0090-3752
Volume: 139
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

The impact of the current nuclear data library covariances such as in ENDF/B-VII.1, JEFF-3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work. The uncertainties due to nuclear data are calculated for existing PWR and BWR fuel assemblies (with burn-up up to 40 GWd/tHM, followed by 10 years of cooling time) and for a simplified PWR full core model (without burn-up) for quantities such as k∞ , macroscopic cross sections, pin power or isotope inventory. In this work, the method of propagation of uncertainties is based on random sampling of nuclear data, either from covariance files or directly from basic parameters. Additionally, possible biases on calculated quantities are investigated such as the self-shielding treatment. Different calculation schemes are used, based on CASMO, SCALE, DRAGON, MCNP or FISPACT-II, thus simulating real-life assignments for technical-support organizations. The outcome of such a study is a comparison of uncertainties with two consequences. One: although this study is not expected to lead to similar results between the involved calculation schemes, it provides an insight on what can happen when calculating uncertainties and allows to give some perspectives on the range of validity on these uncertainties. Two: it allows to dress a picture of the state of the knowledge as of today, using existing nuclear data library covariances and current methods.

More information

Item ID: 49831
DC Identifier: http://oa.upm.es/49831/
OAI Identifier: oai:oa.upm.es:49831
DOI: 10.1016/j.nds.2017.01.001
Official URL: https://www.sciencedirect.com/science/article/pii/S0090375217300017?via%3Dihub
Deposited by: Memoria Investigacion
Deposited on: 03 May 2018 16:31
Last Modified: 01 Feb 2019 23:30
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