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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.
G. Ronald Dalton
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 190-196
Technical Paper | doi.org/10.13182/NSE62-A26147
Articles are hosted by Taylor and Francis Online.
The time and speed independent neutron transport equation in its integral form is applied to the calculation of the disturbed neutron flux in the vicinity of neutron detectors. The method is also applied to the calculation of the average flux in a two-detector system where the detectors are close enough to interact with each other. Hand methods of solving the integral equations are developed and shown to give results in good agreement with more accurate numerical methods of solving the integral equations.