Multi-MOX: Facilitating plutonium multi-recycling in the French PWR fleet

This study examines the Multi-MOX (MMOX) strategy for plutonium multi-recycling in PWRs using the CLASS fuel cycle simulation tool with assembly-level calculations. MMOX facilitates the multi-recycling of used nuclear fuel by mixing reprocessed plutonium from various sources to create viable fresh nuclear fuel. The strategy significantly curtails the growth of the plutonium inventory, but does not stabilize it entirely in the long term. Although lower fuel burnup reduces plutonium build-up, it increases the production of minor actinides. Comparing MMOX with non-recycling and mono-recycling scenarios, we find that it reduces plutonium inventory by 35% and 19%, respectively. Despite a higher level of minor actinide production, MMOX decreases overall transuranic element production. Additionally, MMOX reduces the need for interim spent fuel storage by a factor of ten compared to non-recycling and by two-thirds compared to mono-recycling, while substantially lowering the age of stockpiled used nuclear fuel. • Multi-MOX is a Pu recycling method that mixes reprocessed Pu from various used fuels. • Multi-MOX substantially curbs the growth of the plutonium inventory. • Multi-MOX reduces TRUE production. • Multi-MOX greatly reduces interim storage capacity needed for used nuclear fuel.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-07-01
DOI
https://doi.org/10.1016/j.anucene.2025.111641
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Multi-MOX: Facilitating plutonium multi-recycling in the French PWR fleet

Xavier Doligez, Gulla Serville Torvund, D. Gjestvang, Nicolas Thiollière et al.
Annals of Nuclear Energy
Nuclear reactor physics and engineering
article

Multi-MOX: Facilitating plutonium multi-recycling in the French PWR fleet

Xavier Doligez, Gulla Serville Torvund, D. Gjestvang, Nicolas Thiollière, S. Siem, Fanny Courtin, Marc Ernoult
article en

Abstract

This study examines the Multi-MOX (MMOX) strategy for plutonium multi-recycling in PWRs using the CLASS fuel cycle simulation tool with assembly-level calculations. MMOX facilitates the multi-recycling of used nuclear fuel by mixing reprocessed plutonium from various sources to create viable fresh nuclear fuel. The strategy significantly curtails the growth of the plutonium inventory, but does not stabilize it entirely in the long term. Although lower fuel burnup reduces plutonium build-up, it increases the production of minor actinides. Comparing MMOX with non-recycling and mono-recycling scenarios, we find that it reduces plutonium inventory by 35% and 19%, respectively. Despite a higher level of minor actinide production, MMOX decreases overall transuranic element production. Additionally, MMOX reduces the need for interim spent fuel storage by a factor of ten compared to non-recycling and by two-thirds compared to mono-recycling, while substantially lowering the age of stockpiled used nuclear fuel. • Multi-MOX is a Pu recycling method that mixes reprocessed Pu from various used fuels. • Multi-MOX substantially curbs the growth of the plutonium inventory. • Multi-MOX reduces TRUE production. • Multi-MOX greatly reduces interim storage capacity needed for used nuclear fuel.

Annals of Nuclear EnergyVol. 223
Institut polytechnique de Grenoble (FR), Centre National de la Recherche Scientifique (FR), University of Oslo (NO), Université Paris-Saclay (FR), NORCE Research AS (NO), Laboratoire de Physique Subatomique et des Technologies Associées (FR), IMT Atlantique (FR), Institut National de Physique Nucléaire et de Physique des Particules (FR), Laboratoire de Physique des 2 Infinis Irène Joliot-Curie (FR), Laboratoire de Physique Subatomique et de Cosmologie (FR)
Openalex Percentile: Top 78%
Nuclear reactor physics and engineering
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