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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.
G. Haouat, J. Lachkar, J. Sigaud, Y. Patin, F. Coçu
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 331-346
Technical Paper | doi.org/10.13182/NSE78-A27161
Articles are hosted by Taylor and Francis Online.
Measurements of differential cross sections for fast neutrons scattered by carbon are presented for 14 incident neutron energies between 8.0 and 14.5 MeV. The measurements were performed with the four-detector neutron time-of-flight facility of the Centre d'Etudes de Bruyères-le-Châtel tandem Van de Graaff accelerator. The angular distributions for elastic and inelastic scattering to the first excited level of 12C were obtained over the angular range from 10 to 160 deg. The experimental uncertainties vary from 7 to 15% for the differential elastic scattering cross sections and from 8 to 22% for the differential inelastic scattering cross sections. These measurements partially fill in an energy range that was previously characterized by a lack of data. The angle-integrated cross sections are compared to the evaluated values of ENDF/B, and significant discrepancies are shown. The present data were included in an evaluation work on carbon carried out in this laboratory. The consistency of total cross-section measurements with our data and other partial cross sections is discussed.