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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.
D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 521-533
Technical Paper | doi.org/10.13182/NSE76-A14488
Articles are hosted by Taylor and Francis Online.
A fast-neutron time-of-flight spectrometer has been constructed for the purpose of measuring neutron differential cross sections of interest to the controlled thermonuclear reactor (CTR) program. The experimental facility provides the capability of measuring scattering cross sections of a few mb/sr to ∼5% absolute accuracy in the energy range from 6 to 15 MeV. Source neutrons are provided by the D(d,n)3He reaction. Scattered neutrons are detected at 28 angles between 25 and 160 deg in a massively shielded NE218 liquid scintillator located 4 m from the scattering sample. Absolute cross sections are obtained by normalizing to n-p scattering. Differential elastic and inelastic scattering cross sections are reported for 8.97-, 9.19-, 9.55-, 9.96-, 10.21-, 10.69-, 10.96-, 11.16-, 11.73-, 11.96-, 12.44-, 12.95-, 13.95-, 14.43-, and 14.93- MeV neutrons incident upon high-purity carbon. Monte Carlo simulation has been used to correct for finite source and sample effects. These data partially fill the 9- to 15-MeV gap in the carbon elastic and inelastic scattering data set required for the CTR program.