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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. K. Davis, J. A. De Juren, M. Reier
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 74-81
Technical Paper | doi.org/10.13182/NSE65-A19260
Articles are hosted by Taylor and Francis Online.
Measurements of the shape of the fundamental mode of a thermalized neutron pulse in graphite for rectangular stacks has yielded a value of the extrapolation length, d = 1.825 ± 0.025 cm. The pulsed-neutron decay constants in graphite have been measured over a buckling range from 1.946 × 10−3 to 1.230 × 10−2 cm −2 and fitted to three- and four-term power series in the buckling. To fit points at bucklings greater than 6.0 × 10−3 cm−2, a cubic fit is necessary. An iterative method of fitting the decay constants results in an extrapolation length of 1.78 ± 0.01 cm. The diffusion constant was (2.0896 ± 0.0093) × 105cm2/sec, and the diffusion cooling constant was (3.77 ± 0.35) × 106 cm4/sec at a density of 1.689 g/cm3. A technique of correcting the decay constants for the effect of spectral cooling has been developed. The decay constants corrected to room temperature can be fitted as a linear function of the buckling. This method interates on the heat-transfer coefficient, γ, and gives a value of γ = 1633 ± 89 sec−1 for graphite. The heat-transfer coefficient relates the rate of energy transfer from a moderator to a cooled-neutron spectrum. With this approach the entire buckling range can be fitted with three parameters.