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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.
Y. Naito, M. Maekawa, K. Shibuya
Nuclear Science and Engineering | Volume 58 | Number 2 | October 1975 | Pages 182-192
Technical Paper | doi.org/10.13182/NSE75-A28221
Articles are hosted by Taylor and Francis Online.
A new iterative method is proposed for solving the three-dimensional neutron diffusion equation. This method reduces the discretization error in the calculation of neutron leakage from a subregion. In addition, when only one fine-mesh point is located in each subregion, this method becomes the same as a fine-mesh finite-difference approximation method. Therefore, it is easy to compare the results of this method with those of a fine-mesh difference approximation. The computer code for this method can be used for calculating both the collapsed neutron flux and fine-mesh difference approximations. The conditions for the convergence of this iterative technique are introduced as a function of the neutron leakage.