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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.
D. R. Edwards, K. F. Hansen
Nuclear Science and Engineering | Volume 25 | Number 1 | May 1966 | Pages 58-65
Technical Paper | doi.org/10.13182/NSE66-A17501
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The multigroup diffusion equations are solved by treating them as an initial value problem. The inherent error growth is controlled by repeated conditioning transformations; the error bounds on the final solution are set by the frequency of conditioning. The stabilized march technique (SMT) is comparable in speed to AIM-5 for problems involving downscatter only. The SMT is shown to be relatively insensitive to the type of scatter matrix involved and, hence, presents an advantage for problems with full scatter matrices. The technique is readily adaptable to flux synthesis, and an example is given for expanding the thermal flux in Laguerre polynomials. The SMT performs equally well in calculating higher order eigenvalues and eigenfunctions.