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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.
Richard E. Kaiser, William R. Kimel
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 468-475
Technical Paper | doi.org/10.13182/NSE64-A20989
Articles are hosted by Taylor and Francis Online.
Several methods are available for the determination of thermal diffusion length. In general, those based on one-group diffusion theory are subject to the assumption of a particular source boundary condition. Errors introduced by the assumption of such boundary conditions usually result in incorrect prediction of the relative harmonic content of the thermal flux at different elevations in the pile. The effect of these errors on diffusion-length determination is to cause inconsistency in the results as additional data points taken close to the source are included. A method is presented whereby the constants Amn in the one-group thermal-flux equation are determined experimentally and used in the determination of diffusion length. This method is then compared with other methods using one-group and age-diffusion theory with respect to the consistency of results obtained.