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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.
S. N. Cramer, E. M. Oblow
Nuclear Science and Engineering | Volume 58 | Number 1 | September 1975 | Pages 33-53
Technical Paper | doi.org/10.13182/NSE75-A26765
Articles are hosted by Taylor and Francis Online.
The results of two integral experiments on carbon, performed at the Oak Ridge National Laboratory (ORNL) and at Intelcom Radiation Technology were compared with Monte Carlo calculations to test evaluated carbon neutron and gamma-ray production data sets. In both experiments NE-213 detectors were used to measure the angular dependence of neutron scattering and gamma-ray production from thick (1-mfp) carbon samples in the energy range from 0.5 to 20 MeV. Additional measurements from the ORNL experiment also provided angular-dependent energy distributions of the scattered neutrons. Multigroup Monte Carlo calculations modeling the two experimental arrangements were made to compare with the measured data. Both ENDF/B-III and ENDF/B-IV carbon data were used in the computations. The results indicate that such experiments are adequate for testing processed neutron scattering and gamma-ray production data (both integral and double differential) to within 10 to 20% over a wide range of incident neutron energies (1 to 15 MeV). Also, on the whole, calculations with the carbon ENDF/B-IV data compared favorably with the measured results over the energy range, tested. The only notable exceptions were the disagreements in the neutron result comparisons above 9 MeV, which were attributed for the most part to errors in the evaluated C(n, n’)3α and elastic angular distribution cross sections in this range.