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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. Caro, J. Ligou
Nuclear Science and Engineering | Volume 83 | Number 2 | February 1983 | Pages 242-252
Technical Paper | doi.org/10.13182/NSE83-A18217
Articles are hosted by Taylor and Francis Online.
Handling the highly anisotropic scattering of fast neutrons with conventional methods usually means that high-order Legendre expansions can be necessary to obtain correct angular fluxes. This drawback in standard transport calculations is avoided by applying the Boltzmann-Fokker-Planck (BFP) method, already used in transport of charged particles, to neutrons. Two methods are described to obtain the relevant input data for the one-dimensional BFP-1 code, one using basic differential scattering cross sections and the other using existing standard multigroup libraries. Numerical results for both methods are produced, revealing BFP as a powerful method when solving transport problems dealing with very fast neutrons. It is found that high accuracy, even for extreme cases of anisotropy, is achieved without increase of the computational effort.