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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.
M. M. R. Williams, J. M. Kallfelz
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 416-419
Technical Note | doi.org/10.13182/NSE78-A27170
Articles are hosted by Taylor and Francis Online.
An analysis is made of the accuracy of the buckling approximation for the transverse leakage, used in various one- and two-dimensional transport theory computer codes. We find that the resulting approximate integro-differential form of the transport equation is not suitable for calculating accurate values of the angle-dependent flux for any case where transverse leakage has an appreciable effect on the solution. We have taken four problems, namely, critical equation, pulsed neutron and diffusion length problems, and extrapolated endpoints, and have solved them exactly using an equation derived in an earlier paper; we then solve the same problem by means of the buckling equation. In all cases, important deviations are noted that restrict the use of the buckling approximation.