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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.
K. Serdula, J. Young
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 40-50
Technical Paper | doi.org/10.13182/NSE65-A19761
Articles are hosted by Taylor and Francis Online.
The neutron diffusion and integral scattering properties of graphite have been measured by the pulsed-neutron-source technique. Measurements were performed on assemblies with geometric bucklings from 0.0036 to 0.0151 cm−2. The time of attainment of asymptotic neutron-energy spectra was determined from transmission measurements. Results from these latter measurements indicated that the minimum thermalization time, for the assemblies investigated, was ≈ 2 msec. Asymptotic ‘average’ neutron velocities, measured both internally and externally, were obtained as a function of assembly size. Results indicated that an asymptotic neutron spectrum did not exist for assemblies with B2 ≈ 0.015 cm−2 at a time 2 msec after the neutron pulse. A value of the diffusion cooling coefficient, C = 45.6 ± 4.7 × 105 cm4/sec was derived from the measured ‘thermal’ neutron decay constants.