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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.
S. S. Glickstein, P. H. Lehmann, L. L. Wheat, J. D. Korsmeyer, S. Milani, G. G. Smith, S. H. Weiss
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE67-A17249
Articles are hosted by Taylor and Francis Online.
Thermal disadvantage factor measurements in cells of seed-blanket assemblies containing highly enriched 235U and 233U fuel rods as well as in cells containing slightly enriched 233U fuel rods are in agreement within experimental uncertainties with calculations for all but a very tightly packed blanket lattice. The measurements were corrected for flux perturbations in the fuel rod and the moderator channel caused by the detecting foils. MARC calculations using the Radkowsky scattering kernel yield results approximately 8% higher than similar calculations using the Nelkin kernel. While THERMOS calculations for the tightly packed blanket cells appear to be in agreement with measurement (possibly fortuitous), MARC results are significantly above the measured values. The source of the discrepancy is not known at this time. Higher order scattering as well as angular energy effects in the source-to-thermal neutron energy treatment have been investigated using a newly developed full energy range (0 to 10 MeV) Monte Carlo program RECAP-4C.
