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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.
George E. Apostolakis
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 141-152
Technical Paper | doi.org/10.13182/NSE74-A23340
Articles are hosted by Taylor and Francis Online.
This is a theoretical investigation of the accuracy of conventional point kinetics in a multiregion reactor without feedback. The fundamental assumption of point kinetics is the splitting of the neutron density into a product of a known constant shape function and an unknown amplitude function. The model cannot acount for the distortion of the shape of the neutron distribution due to space-dependent perturbations and this results in an error in reactivity. It is to this error that bounds are derived. This is done by using the method of weighted residuals to reduce the original eigenvalue problem to that of a real asymmetric matrix. Theorems from matrix algebra are then used to find disks in the complex plane where the eigenvalues are contained. The radii of the disks depend on the perturbation in a simple manner. Examples of space-dependent step and ramp insertion of reactivity in slab reactors demonstrate the usefulness of the bound.