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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. Necati Özişik, H. J. de Nordwall
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 310-319
Technical Paper | doi.org/10.13182/NSE71-A20164
Articles are hosted by Taylor and Francis Online.
The rate, extent, and spatial variation of carbon loss from a graphite cylinder exposed to steam has been calculated as a function of time. The geometrical arrangement considered was a hollow cylinder with a helium-steam mixture on the inside. At the outer boundary either a zero concentration or a zero steam flux may be maintained. The reaction was assumed to be first order. Changes in the rate of carbon removal with time other than those associated with establishing a steady-state steam concentration gradient were not considered. Calculations using constants derived from current experimental work lead one to conclude that the time needed to establish a concentration gradient is insignificant compared with the times for which the hot core of a high-temperature gas-cooled reactor could be exposed to steam accidentally. This conclusion could change if much tighter graphites or more massive sections, equivalent to thicker cylinders in our analysis, were to be used.