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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.
W. E. Loewe, W. A. Turin, C. W. Pollock, A. C. Springer, B. L. Richardson
Nuclear Science and Engineering | Volume 85 | Number 2 | October 1983 | Pages 87-115
Technical Paper | doi.org/10.13182/NSE83-A27418
Articles are hosted by Taylor and Francis Online.
The results of a program are reported whose objective has been to establish the reliability and accuracy of tissue kerma estimates near the ground, out to deep penetration ranges, from a point neutron source in an air-over-ground geometry. The results take the form of expected error in calculated neutron and secondary gamma-ray kerma out to 2-km range for any neutron source height and energy spectrum. In the first of two approaches, experimental data permitting absolute evaluation in one dimension is used in conjunction with an evaluated calculational procedure for two dimensions to obtain overall error estimates. In the second approach, errors obtained from comparisons of measurement and calculation in air-over-ground geometry are evaluated to obtain overall error estimates. When the results of these two approaches are averaged, it can be concluded with confidence that kerma to 2 km will probably be calculated to be 10 to 15% lower than measured values for neutrons and 20 to 25% lower for gamma rays when this cross-section set and recommended calculational procedure or equivalents are used.