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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.
Mark W. Crump, John C. Lee
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 192-210
Technical Paper | doi.org/10.13182/NSE81-A21353
Articles are hosted by Taylor and Francis Online.
We present a new computational method developed for fluid flows, in which both compressibility and thermal expansion effects are important. Application of the method in transient thermal-hydraulic analysis of nuclear steam generators is also presented. The fluid model is based on one-dimensional, nonlinear, single-fluid conservation equations for mass, momentum, and energy. An empirical slip flow model is included to enable description of two-phase flows as well as single-phase flows. Numerical solution is based on the implicit continuous-fluid Eulerian (ICE) method, which provides stable numerical solutions for compressible fluid flows. An extension of this method (designated as the EICE method) is developed to account for thermal expansion effects. This is achieved by including implicit energy dependence in coupled equations of mass, momentum, and state, and solving the full system of fluid equations through a two-step iterative technique. The development of the EICE method is presented and discussed, along with specific calculations for once-through and U-tube steam generator transients, natural flow oscillations, and a vessel blowdown transient.