Proliferation-resistant fuel in a continuously refuelled operation cycle of a molten-salt reactor

Nuclear energy is widely regarded as a key contributor to achieving a carbon-neutral energy landscape due to its ability to generate large-scale power with minimal emissions of greenhouse gases. Advances in Generation IV reactor technology, particularly in the effort to develop molten salt reactors (MSRs), are enhancing this potential by focusing on improvements in safety, efficiency, and sustainability. MSRs utilise liquid salt as both a coolant and a fuel, a design that inherently enhances safety and thermal efficiency. Nevertheless, nuclear proliferation remains a critical obstacle, particularly in designs utilising the uranium-plutonium cycle, to the broader acceptance and adoption of nuclear power. This paper explores the integration of Am-241 into MSR fuel as a method to provide proliferation-resistant operation. Incorporating Am-241 enhances the production of Pu-238, which paves the way for fuels considered resistant to proliferation while preserving the reactor’s operational feasibility. Although Am-241 has neutron-absorbing characteristics, MSRs mitigate this challenge through continuous operation and dynamic refuelling. Economic analysis indicates that the Am-241 doping approach results in a levelized cost of electricity increase of approximately $10/MWh over a 60-year operational lifetime, representing less than 15% of typical nuclear LCOE. This cost premium is economically acceptable when evaluated against the passive nonproliferation benefits provided. Future integration with spent fuel reprocessing programmes could further reduce costs by recovering Am-241 from LWR spent fuel, potentially decreasing the economic impact by 50–70%.

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Publication Details

Journal
Next Energy
Published
2026-03-21
DOI
https://doi.org/10.1016/j.nxener.2026.100583
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Proliferation-resistant fuel in a continuously refuelled operation cycle of a molten-salt reactor

Marat Margulis, Mustafa J. Bolukbasi
Next Energy
Nuclear reactor physics and engineering
article

Proliferation-resistant fuel in a continuously refuelled operation cycle of a molten-salt reactor

Marat Margulis, Mustafa J. Bolukbasi
article en

Abstract

Nuclear energy is widely regarded as a key contributor to achieving a carbon-neutral energy landscape due to its ability to generate large-scale power with minimal emissions of greenhouse gases. Advances in Generation IV reactor technology, particularly in the effort to develop molten salt reactors (MSRs), are enhancing this potential by focusing on improvements in safety, efficiency, and sustainability. MSRs utilise liquid salt as both a coolant and a fuel, a design that inherently enhances safety and thermal efficiency. Nevertheless, nuclear proliferation remains a critical obstacle, particularly in designs utilising the uranium-plutonium cycle, to the broader acceptance and adoption of nuclear power. This paper explores the integration of Am-241 into MSR fuel as a method to provide proliferation-resistant operation. Incorporating Am-241 enhances the production of Pu-238, which paves the way for fuels considered resistant to proliferation while preserving the reactor’s operational feasibility. Although Am-241 has neutron-absorbing characteristics, MSRs mitigate this challenge through continuous operation and dynamic refuelling. Economic analysis indicates that the Am-241 doping approach results in a levelized cost of electricity increase of approximately $10/MWh over a 60-year operational lifetime, representing less than 15% of typical nuclear LCOE. This cost premium is economically acceptable when evaluated against the passive nonproliferation benefits provided. Future integration with spent fuel reprocessing programmes could further reduce costs by recovering Am-241 from LWR spent fuel, potentially decreasing the economic impact by 50–70%.

Next EnergyVol. 11
Bangor University (GB), University of Derby (GB)
Openalex Percentile: Top 11%
Nuclear reactor physics and engineering
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