Open Access
ND 2007
Article Number 237
Number of page(s) 4
Section Fission applications
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07468

Systematic analysis of actinide decay heat focused on the mixed oxide fuel

N. Hagura1, T. Yoshida1 and T. Nakagawa2

1  Musashi Institute of Technology, 1-28-1 Tamazutsumi, Setagaya-ku, Tokyo 158-8557, Japan
2  Nuclear Data Center, Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

Published online: 21 May 2008

Radioactivity and decay power of spent MOX fuel are very crucial in term of storage or disposal. In this work, the uncertainty of actinide decay heat introduced by the uncertainty of nuclear data and the prediction accuracy of isotopic generation was studied. 100 year after discharge, for example, a 5% error on the decay heat will be introduced by a 20% uncertainty on the Pu-240 capture cross section through Am-241 production. We performed sensitivity analyses with covariance data in JENDL-3.3 of cross sections of notable nuclides on each energy group. As an example, standard deviation of the calculated actinide decay heat 100 year after discharge is evaluated to be 1.26% on a 1σ base.

© CEA 2008