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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.
R. A. Bennett, R. E. Heineman
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 294-299
Technical Paper | doi.org/10.13182/NSE60-A28859
Articles are hosted by Taylor and Francis Online.
The thermal neutron absorption rate in “1/v” materials has been observed near a discontinuity in the temperature of a graphite moderator. A plausible group diffusion model of the space and energy distributions of the thermal neutrons has been assumed. The experimental data have been used to obtain the transfer cross sections, called rethermalization cross sections, to be used with this model. The cross sections obtained for crystalline graphite are small compared to those expected for gaseous graphite; but they increase by a factor of about seven, from (1.9 ± 0.05) × 10−3 to (14.5 ± 2.6) × 10−3 cm−1, from the lowest temperature of 108°K to the highest temperature of 666°K.