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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.
Yoshihiko Kaneko, Fujiyoshi Akino, Yoshiro Suzuoki, Kenji Kitadate, Ryosuke Kurokawa,Kinji Koyama
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 105-116
Technical Note | doi.org/10.13182/NSE74-A23974
Articles are hosted by Taylor and Francis Online.
Neutron diffusion coefficients were measured in square lattices of aluminum channels in light water in both the axial and the radial directions by the pulsed neutron technique. The diameter of the channels was 15 mm and the pitch of the lattice was 19 or 24 mm. Good agreement was observed between the experimental values of the axial diffusion coefficient, Da, and those calculated by the two-dimensional discrete Sn method. In this calculation, the value of the diffusion coefficient was interpreted as the slope of the decay constant as a function of the geometrical buckling in the axial direction of the channels. Also, the measured values of the radial diffusion coefficients agreed well with those calculated by the well-known Benoist practical formulas. The relation between the extrapolation distance and the effective transport length in the axial direction, ℓa and 3Da/V was numerically investigated. The ratio of the former to the latter is found to be considerably higher than the value of 0.71 used hitherto.