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August 24–27, 2026
Dallas, TX|Hilton Anatole
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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.
Wayne A. Houlberg, Robert W. Conn
Nuclear Science and Engineering | Volume 64 | Number 1 | September 1977 | Pages 141-150
Technical Paper | doi.org/10.13182/NSE77-A27085
Articles are hosted by Taylor and Francis Online.
Research on the development of numerical techniques to simulate the space-time evolution of large tokamak plasmas is reported. A nonuniform spatial mesh technique is employed to allow more accurate calculations in the boundary of reactor-size plasmas. A box integration method is used to maintain the accuracy of central differencing on the nonuniform spatial mesh and to preserve both the particle and energy flux. A variable implicit technique is used for the time expansion. The time-centered (Crank-Nicholson) technique used in most other models generally offers greater accuracy but can lead to severe limitations on the time step. Somewhat more implicit treatments can remove the numerical limitations on the time step without seriously affecting accuracy. The physical time scales, which can change by several orders of magnitude from startup to equilibrium, can then be used to continually adjust the time step throughout a calculation. Sample calculations are presented for a near-term tokamak engineering test reactor and a conceptual tokamak power reactor, UWMAK-III.