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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.
Gert Van den Eynde, Robert Beauwens, Ernest Mund
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 300-309
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2664
Articles are hosted by Taylor and Francis Online.
The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.