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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.
R. Sanchez, B. D. Ganapol
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 61-66
Technical Note | doi.org/10.13182/NSE83-A17458
Articles are hosted by Taylor and Francis Online.
The integral transform method (ITN) has been extended to the treatment of one-dimensional homogeneous media with linearly anisotropic scattering. A previously obtained formula linking the isotropic and the anisotropic one-dimensional kernels allows for calculation of the anisotropic matrix elements in the form of linear combinations of a few isotropic matrix elements. In practice, to solve the anisotropic problem of order N one needs only to calculate the isotropic collision matrix of order (N + 2) in plane and spherical geometries and of order (N + 1) in cylindrical geometry. The method is applied to the calculation of critical parameters for bare cylinders. Highly accurate values, to be used as benchmarks, are obtained and illustrate the precision and fast convergence rate of the method.