Open Access
| Issue |
ND 2007
2007
|
|
|---|---|---|
| Article Number | 241 | |
| Number of page(s) | 4 | |
| Section | Fission applications | |
| DOI | https://doi.org/10.1051/ndata:07644 | |
| Published online | 17 June 2008 | |
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07644
1 LPSC, Université Joseph Fourier Grenoble 1, CNRS/IN2P3, Institut National Polytechnique de Grenoble, France
2 Institut de Physique Nucléaire d'Orsay, IN2P3/CNRS, 91406 Orsay, France
bidaud@lpsc.in2p3.fr
Published online: 21 May 2008
© CEA 2008
DOI: 10.1051/ndata:07644
Direct sensitivity analysis to nuclear data of thorium molten salt reactors at equilibrium using MURE
A. Bidaud1, O. Meplan2, A. Nuttin1, S. David2, J.N. Wilson2, F. Michel-Sendis2, P. Guillemin1 and N. Capellan21 LPSC, Université Joseph Fourier Grenoble 1, CNRS/IN2P3, Institut National Polytechnique de Grenoble, France
2 Institut de Physique Nucléaire d'Orsay, IN2P3/CNRS, 91406 Orsay, France
bidaud@lpsc.in2p3.fr
Published online: 21 May 2008
Abstract
In this paper we propose to use the MURE (MCNP Utility for Reactor Evolution) package to calculate directly nuclear data sensitivities of the breeding gain of a thorium molten salt reactor. The continuous fuel reprocessing is used to control reactivity. This control coupled with the fact that the fuel has reached its equilibrium, induces feedback effects on nuclear data sensitivities. That is why sensitivities are calculated directly by recalculating the fuel equilibrium of a simplified model after modifications of the ACE files for the reactions that are expected to have the strongest contribution to the uncertainty: 233U capture cross section and neutron fission yield.
© CEA 2008