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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.
P. A. Egelstaff, P. Schofield
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 260-270
Technical Paper | doi.org/10.13182/NSE62-A26066
Articles are hosted by Taylor and Francis Online.
The magnitude of the scattering cross section for slow neutrons by atomic systems (gases, liquids, and polycrystalline solids) is governed by the correlated motions of atoms in the system. A major contribution to the scattering is determined by the motion of single atoms. The dominant part of this contribution is determined by the velocity autocorrelation function for an atom in the system. The aim of this paper is (i) to show how the autocorrelation function can be derived from experimental scattering data for small momentum transfers and (ii) to give methods of evaluation of the corresponding part of the cross section for all momentum and energy transfers in terms of the experimentally observed quantities. The methods are chosen to minimise computational difficulties and inaccuracies. The comparison of the recomputed data with the experimental results permits the estimate of other contributions to the scattering. Some simple examples of these methods are given, and the relevance of this work to thermal neutron transport calculations is mentioned.