Skip to Main content Skip to Navigation
Journal articles

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

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.
Document type :
Journal articles
Complete list of metadata

https://hal.archives-ouvertes.fr/hal-01554592
Contributor : Inspire Hep Connect in order to contact the contributor
Submitted on : Monday, July 3, 2017 - 6:03:54 PM
Last modification on : Wednesday, January 12, 2022 - 10:21:49 PM

Links full text

Identifiers

Citation

D. Rochman, O. Leray, M. Hursin, H. Ferroukhi, A. Vasiliev, et al.. Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core. Nucl.Data Sheets, 2017, 139, pp.1-76. ⟨10.1016/j.nds.2017.01.001⟩. ⟨hal-01554592⟩

Share

Metrics

Les métriques sont temporairement indisponibles