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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.
Rodolfo M. Ferrer, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 33-51
Technical Paper | doi.org/10.13182/NSE10-106
Articles are hosted by Taylor and Francis Online.
A reformulation of the arbitrarily high-order transport method of the characteristic type (AHOT-C) for unstructured grids (AHOT-C-UG) is presented in this work, which resolves the previous difficulties encountered in the original formalism. A general equivalence between the arbitrary-order neutron balance and arbitrary-order characteristic equations is derived, which improves the numerical computation of the spatial moments of the angular flux and allows a series expansion of the characteristic integral kernel in cases where the medium is optically thin. Numerical results are presented, which verify the convergence behavior of AHOT-C-UG for various expansion orders.