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Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
Hyunsuk Lee, Sooyoung Choi, Deokjung Lee
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 69-85
Technical Paper | doi.org/10.13182/NSE13-102
Articles are hosted by Taylor and Francis Online.
This paper proposes a new hybrid method combining the Monte Carlo (MC) method and the Method of Characteristics (MOC). The hybrid method employs MC and MOC together to solve a neutron transport problem. The two different methods are applied to different neutron energy ranges. The MC method is used to obtain accurate solutions in the resonance energy range, and the MOC is used for high and low neutron energy ranges to achieve high performance of the new method. The two methods are consistently coupled through scattering and fission source terms during the power iterations and group sweepings. Numerical tests with a model problem confirm that the hybrid method can produce a more accurate solution than a conventional MOC by a factor of 10 and much higher computational efficiency than a conventional MC method by a factor of 90.