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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. J. Grady, G. F. Knoll, J. C. Robertson
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 227-232
Technical Paper | doi.org/10.13182/NSE86-A17265
Articles are hosted by Taylor and Francis Online.
The neutron capture cross section in 115In leading to the 54.12 min isomeric state (m1) in 116In has been absolutely determined at neutron energies of 23, 265, and 964 keV. These energies are the median neutron energies of the three photoneutron sources, Sb-Be, Na-D, and Na-Be, applied in this work. The measurements are independent of other cross-section data except for corrections amounting to <10%. Reaction rates were determined by beta counting of the 116m1In decay activity using a 4π gas flow proportional counter. Detector efficiency was measured using 4π beta-gamma coincidence counting techniques, incorporating the foil absorber method of efficiency extrapolation for correction of complex decay scheme effects. Photoneutron source emission rates were determined by indirect comparison with the U.S. National Bureau of Standards NBS-II standard source in the University of Michigan Manganese Bath. The normalized scalar flux was calculated from the neutron emission angular distribution results of a Monte Carlo computer program used to model neutron and gamma transport in the source. Correction factors were applied related to competing reactions, neutron scattering from experiment components, background from room-return neutrons, and differences in the energy spectra of the neutron sources. The absolute cross-section values obtained for the 115In(n, γ)116m1In reaction were 588 ± 11, 196 ± 4, and 203 ± 4 mb at 23, 265, and 964 keV, respectively.