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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.
Seong-Youn Kim, Raphael Aronson
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 56-65
Technical Paper | doi.org/10.13182/NSE80-A18708
Articles are hosted by Taylor and Francis Online.
The transfer matrix method is used to solve the Milne problem for a half space for neutrons interacting with a moderator at temperature T. Two different scattering models are considered. They are (a) the free monatomic gas of arbitrary molecular mass with constant cross sections in the center-of-mass system, and (b) the Nelkin kernel for water. Both models permit an additional 1/v absorption cross section. We have obtained accurate numerical values for the diffusion length, the extrapolated end point, the critical absorption strength, and the boundary heating for a variety of values of the parameters. Comparison is made both with other calculations and with experiments.