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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.
Frank Kedziur
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 9-22
Technical Paper | doi.org/10.13182/NSE82-A19591
Articles are hosted by Taylor and Francis Online.
Stationary two-phase flow experiments at pressures up to 13 MPa and temperatures up to 600 K have been performed in a converging nozzle. The experiment is specially designed for the assessment of two-phase computer codes used in reactor safety analysis, in particular for loss-of-coolant accident blowdown calculations. An assessment by the codes DUESE, DRIX-2D, and RELAP4/MOD6 is reported. The shape of the nozzle, the instrumentation, and the experimental program are such that models and empirical parameters of a wide range of codes can be tested and determined, respectively. Results show the influence and magnitude of models and parameter variations, the effect of the dimensionality and the difference scheme of the code, and the relevance of the models as a function of the initial conditions.