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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.
W. R. Gambill, R. D. Bundy
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 69-79
Technical Paper | doi.org/10.13182/NSE64-A18141
Articles are hosted by Taylor and Francis Online.
In support of the High Flux Isotope Reactor Program, experimental determinations were made of friction factors, burnout heat fluxes, and average and local nonboiling heat-transfer coefficients for forced-convection flow of water through thin aluminum and nickel rectangular channels under the following conditions: heat flux = 0.1 × 106 to 7.4 × 106 Btu/h·ft2, velocity = 10 to 85 ft/sec, Reynolds number = 9,000 to 270,000, pressure = 1 to 39 atmospheres absolute, flow gap = 0.043 to 0.057 in., and heated length = 12 and 18 in. A few tests were made to ascertain the effect of an axially oriented cylindrical spacer strip on surface-temperature distribution and burnout heat flux. The results of these studies, unlike those of some earlier investigations of narrow-gap heat transfer, are in reasonably good agreement with accepted correlations. The friction factors are in satisfactory agreement with the Moody chart for the relative roughness of the test sections used, the burnout heat fluxes are well reproduced by the Soviet Zenkevich-Subbotin correlation, and the local and average heat-transfer coefficients are slightly larger than values predicted by the Hausen and Sieder-Tate equations.