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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.
G. P. Sabol, S. G. McDonald
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 83-90
Technical Paper | doi.org/10.13182/NSE77-A27007
Articles are hosted by Taylor and Francis Online.
Alloying additions of 0.5 and 1.0 wt% niobium, respectively, have been added to Zircaloy-4 in an attempt to improve its high-temperature corrosion resistance. Ingots of these modified alloys were fabricated to a 0.76-mm-thick sheet via a processing sequence compatible with commercial tubing production and were given one of four different final anneals. Subsequent testing indicated that the niobium additions had little or no effect on corrosion resistance in 360°C water. In 427°C steam, however, the 0.5%-niobium addition provided increased resistance to spalling, while the 1.0%-niobium addition decreased both cumulative weight gains and post-transition corrosion rates. The weight gains exhibited by the 0.5%-niobium alloy were relatively insensitive to final heat treatment, whereas the 1.0%-niobium alloy suffered a degradation in properties as the extent of the final anneal increased. These trends in corrosion performance were subsequently correlated with the second-phase particle size distributions present in the alloys, the best performance being obtained when the mean particle diameter was <400 to 500 Å. It was concluded that both niobium additions improved the corrosion performance of Zircaloy-4 at elevated temperatures, but that the best performance was obtained at the 1.0-wt%-niobium level.