Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

Schillebeeckx P.
Leal L.
De Saint Jean C.
Vidal J.F.
Peneliau Y.
Blaise P.
Leconte P.
Bernard D.
Bouland O.
Noguere G.
Kopecky S.
Lampoudis C.

Open link

Publication date

March 2013

DOI

10.1051/epjconf/20134205005

Publisher

EDP Sciences

Journal

EPJ Web of Conferences

Abstract

Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240