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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.
Suresh M. Lee, R. Vaidyanathan
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE80-A19287
Articles are hosted by Taylor and Francis Online.
A systematic comparison has been made of the local difference operator approximation in spatial difference schemes for the solution of the transport equation in slab geometry by the method of discrete ordinates. The truncation error in different schemes varies according to the nature of the intra-mesh source and flux interpolation, and this explains the good performance of certain recently proposed schemes. We have classified the schemes according to the nature of the intra-mesh source interpolation. As a general principle, we find that in each class, the scheme that conserves the spatial moments of source calculated from the previous iteration and avoids flux interpolation is the most accurate.