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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.
M. D. Fitzsimmons, W. L. Pearl, M. Siegler
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 18-29
Technical Paper | doi.org/10.13182/NSE63-A17206
Articles are hosted by Taylor and Francis Online.
A versatile boiling water and superheated steam facility has been developed for out-of-pile corrosion testing of materials that are being used and considered for application in boiling water reactor (BWR) and superheat reactor (SHR) systems. The following capabilities have been achieved: 1. Simulation of the various environments (other than irradiation) that would contact materials in a Dresden type BWR and an SHR utilizing steam generated therefrom. Test space is available at 1000 psi in saturated steam, steam-water mixture and saturated water at 546°F and in superheated steam at 1050°F. 2. Dynamic fuel-cladding material tests operated with a heat flux of 250,000 Btu/hr-ft2 for testing tubular type cladding under representative BWR heat transfer conditions. 3. Dynamic fuel-cladding-material tests operated with a heat flux of 170,000 Btu/hr-ft2 for testing tubular cladding under representative SHR heat-transfer conditions. 4. Control of oxygen and hydrogen content in the steam and water to simulate the gas conditions from radiolytic water decomposition found in a BWR. 5. Attainment of metal temperatures of 1300°F while superheating steam to 1050°F.