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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.
Francis H. Lewis, Patrick D. Soran
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 116-125
Technical Note | doi.org/10.13182/NSE78-A27277
Articles are hosted by Taylor and Francis Online.
Monte Carlo neutron transport calculations of critical radii of bare UH3 spheres as a function of 233U and 235U enrichment in 238U were carried out using three different calculational methods: 1. the continuous-energy 2. method the multigroup approximation 3. the probability table method. Also calculated were the average neutron removal lifetimes and median fission-producing neutron energies for these critical systems. Results of these calculations were analyzed and compared to quantify and bound self-shielding effects arising from the neutron cross-section resonances in calculating these moderated critical assemblies. Although the critical radii of these assemblies are sensitive to the resonances in 238U, the removal lifetime seems to be affected much more by the fissile isotope resonances. The probability table method gives results that are in excellent agreement with continuous-energy calculations, thereby eliminating the need for special cross-section processing for each separate enrichment when using multigroup cross sections.