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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. D. Bloom, J. M. Green, H. W. Hubbard, S. A. Moszkowski
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 255-265
Technical Paper | doi.org/10.13182/NSE71-A22359
Articles are hosted by Taylor and Francis Online.
Calculations are presented of total cross sections for the following five neutron-induced processes on 56Fe: (n,γ), (n,n’), (n,p), (n,2n), and (n,np), at neutron energies ranging from 10 keV to 18 MeV, depending on the process. The calculations were carried out using the ABACUS-NEARREX code modified by the addition of a subroutine which modeled statistically the final-state level distributions whenever experimental data were lacking. The statistical parameters for the level density formula used in this subroutine were obtained by normalizing to experimental level densities in 56Fe and 56Mn, and to low energy (7 MeV) (n,n’) and (n,p) cross sections. The parameters so derived are in good agreement with those derived from the nuclear shell model. In general, the agreement between the calculations and the experimental cross sections for the five processes enumerated is excellent. It appears clear that the compound statistical model is very good for predicting total reaction rates of this type.