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Energies 2015, 8(11), 12557-12572; doi:10.3390/en81112328

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

1
Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstrasse 400, Dresden 01328, Germany
2
Center for Materials and Structure, University of Liverpool, Liverpool, Merseyside L69 3BX, UK
*
Author to whom correspondence should be addressed.
Academic Editor: Hiroshi Sekimoto
Received: 4 September 2015 / Revised: 21 October 2015 / Accepted: 23 October 2015 / Published: 5 November 2015
(This article belongs to the Special Issue Sustainable Future of Nuclear Power)
View Full-Text   |   Download PDF [1632 KB, uploaded 5 November 2015]   |  

Abstract

An efficient burning of the plutonium produced during light water reactor (LWR) operation has the potential to significantly improve the sustainability indices of LWR operations. The work offers a comparison of the efficiency of Pu burning in different reactor configurations—a molten salt fast reactor, a LWR with mixed oxide (MOX) fuel, and a sodium cooled fast reactor. The calculations are performed using the HELIOS 2 code. All results are evaluated against the plutonium burning efficiency determined in the Consommation Accrue de Plutonium dans les Réacteurs à Neutrons RApides (CAPRA) project. The results are discussed with special view on the increased sustainability of LWR use in the case of successful avoidance of an accumulation of Pu which otherwise would have to be forwarded to a final disposal. A strategic discussion is given about the unavoidable plutonium production, the possibility to burn the plutonium to avoid a burden for the future generations which would have to be controlled. View Full-Text
Keywords: plutonium; plutonium management; plutonium burning; nuclear reactors; molten salt reactor (MSR); fast reactor; light water reactor; mixed oxide (MOX) fuel plutonium; plutonium management; plutonium burning; nuclear reactors; molten salt reactor (MSR); fast reactor; light water reactor; mixed oxide (MOX) fuel
This is an open access article distributed under the Creative Commons Attribution License which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. (CC BY 4.0).

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MDPI and ACS Style

Merk, B.; Litskevich, D. On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study. Energies 2015, 8, 12557-12572.

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