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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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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.
Yuzo Fukai
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 345-354
Technical Paper | doi.org/10.13182/NSE62-A26176
Articles are hosted by Taylor and Francis Online.
In calculating a closely packed lattice, it is well known that one-velocity integral transport theory is the most useful method. Results are briefly presented for calculation of the ratio of moderator to fuel flux in a lattice, , by first and second approximations which have been developed by Corngold. In order to compare these approximations with various other calculating methods, some approximate formulations of a penetrability factor are discussed. After comparing the numerical results from the first and second approximations with the ones of Wachspress, Amouyal, Bengston, and the blackness method, the second approximation is considered to be the best. Consequently the values of the flux ratio in a lattice of fuel cylinders are calculated by using a unit cell method, and the second approximation in the case of a slab lattice which has a mean chord length equivalent to that of the actual lattice, and the results are compared with experiment.