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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.
Michael B. Stanka, James M. Adams, Charles M. Eisenhauer
Nuclear Science and Engineering | Volume 134 | Number 1 | January 2000 | Pages 68-76
Technical Paper | doi.org/10.13182/NSE00-A2100
Articles are hosted by Taylor and Francis Online.
Proton recoil measurements of the 252Cf fission neutron leakage spectrum from a 50-cm-diam iron sphere are performed as a means of checking the degree to which the ENDF/B-VI iron inelastic scattering cross section resolves the well-known discrepancy between predicted and observed neutron transport. These measurements were performed at the National Institute of Standards and Technology using a rotating proton-recoil spectrometer over an energy range of 50 keV to 4.5 MeV. In addition, Monte Carlo neutron transport calculations were performed of the iron-moderated neutron spectrum generated in the experiment. Below 1 MeV, the spectral measurements are in good agreement with a corresponding calculation for the iron-moderated neutron leakage spectrum obtained using the ENDF/B-VI cross-section library. However, the calculation continues to underpredict the neutron fluence above 1 MeV by as much as 11%, which is greater than the average statistical uncertainty of the measured data. Finally, the measurements are compared with those obtained from a similar set of experiments made by two different laboratories in the Czech Republic. The results compare favorably with both of these measurements and indicate the best agreement with the Monte Carlo transport calculations with respect to the integral neutron fluence.