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Poster communications

Direct sensitivity analysis to nuclear data of thorium molten salt reactors at equilibrium using MURE

Abstract : Sustainability and deployment potential of GEN IV reactors is linked to their breeding capacity. Therefore, nuclear data uncertainties should be assessed carefully so as to demonstrate the confidence that we have on the simulation of this key parameter. Breeding fissile material requires the reprocessing of the fuel. Then the actinide content after refueling depends on previous fuel evolutions and so does the sensitivity of any observable linked to these nuclides. Furthermore, keeping the reactor critical at all time can imply strong feedback on the sensitivity calculations too. First results using analytical tools and the equilibrium approach have shown that very strong error compensation may occur because of reprocessing. This means that breeding sensitivities cannot be based on static calculations or one stage evolution calculations. In this paper we propose to use the MURE package to confirm our previous results. Our test case is a Thorium Molten Salt Reactor. It is particularly important to do uncertainty calculations for this reactor concept as the breeding is more difficult to obtain with thorium when nuclear data is known not to be as much validated as for uranium. We will recalculate the fuel equilibrium 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.
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Poster communications
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http://hal.in2p3.fr/in2p3-00186940
Contributor : Lpsc Bibliotheque <>
Submitted on : Tuesday, November 13, 2007 - 9:09:43 AM
Last modification on : Wednesday, September 16, 2020 - 4:08:29 PM

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A. Bidaud, O. Méplan, A. Nuttin, S. David, J. Wilson, et al.. Direct sensitivity analysis to nuclear data of thorium molten salt reactors at equilibrium using MURE. International Conference on Nuclear Data for Science and Technology, Apr 2007, Nice, France. EDP Sciences, pp.919, 2008, ⟨10.1051/ndata:07644⟩. ⟨in2p3-00186940⟩

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