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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.
João Moreira, John C. Lee
Nuclear Science and Engineering | Volume 98 | Number 3 | March 1988 | Pages 244-254
Technical Paper | doi.org/10.13182/NSE88-A22325
Articles are hosted by Taylor and Francis Online.
Control rod worth measurements through the inverse kinetics equation depend on accurate determination of the amplitude function from detector signals. The modal-local method introduced in a previous study estimates space-time changes in the flux or shape function so that the amplitude function can be determined accurately and efficiently. A simple thermal-hydraulic feedback model is included in the modal-local method for at-power reactivity analysis. The method is tested with two simulated rod worth measurements: a zero-power rod drop experiment and a differential rod worth measurement in a power reactor. The modal-local method reproduces the reactivity obtained with the FX2-TH time-dependent diffusion theory code with an overall accuracy of 1 to 2%, except for simulated detectors located in the immediate vicinity of the rod motion.