| Issue |
2014
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
|
|
|---|---|---|
| Article Number | 02409 | |
| Number of page(s) | 9 | |
| Section | 2. Computational Science: d. Basic Physical Data and Uncertainty - Sensitivity Computation | |
| DOI | https://doi.org/10.1051/snamc/201402409 | |
| Published online | 06 June 2014 | |
Probabilistic approach for decay heat uncertainty estimation using URANIE platform and MENDEL depletion code
1 CEA/DEN/DANS/DM2S/SERMA, 91191 Gif-sur-Yvette Cedex, France
2 CEA/DEN/DANS/DM2S/STMF, 91191 Gif-sur-Yvette Cedex, France
* Corresponding Author, E-mail: aime.tsilanizara@cea.fr
The knowledge of the decay heat quantity and the associated uncertainties are important issues for the safety of nuclear facilities. Many codes are available to estimate the decay heat. ORIGEN, FISPACT, DARWIN/PEPIN2 are part of them. MENDEL is a new depletion code developed at CEA, with new software architecture, devoted to the calculation of physical quantities related to fuel cycle studies, in particular decay heat.
The purpose of this paper is to present a probabilistic approach to assess decay heat uncertainty due to the decay data uncertainties from nuclear data evaluation like JEFF-3.1.1 or ENDF/B-VII.1. This probabilistic approach is based both on MENDEL code and URANIE software which is a CEA uncertainty analysis platform. As preliminary applications, single thermal fission of uranium 235, plutonium 239 and PWR UOx spent fuel cell are investigated.
Key words: MENDEL / URANIE / uncertainty / decay heat
© Owned by the authors, published by EDP Sciences, 2014