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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. V. Speight
Nuclear Science and Engineering | Volume 37 | Number 2 | August 1969 | Pages 180-185
Technical Paper | doi.org/10.13182/NSE69-A20676
Articles are hosted by Taylor and Francis Online.
The influence of intragranular bubbles, acting as efficient trapping sites, on the migration of fission gas atoms in material under irradiation is assessed. It is considered that the bubbles are unstable due to the operation of an irradiation-induced resolution process tending to dissolve their enclosed gas. Treating an individual grain within the material as a sphere whose boundary behaves as a perfect sink, general expressions are derived for the intragranular concentrations of gas existing instantaneously within bubbles and in solution. It is shown that the relationships may be simplified for the range of irradiation times and conditions likely to be encountered in practice. Under these conditions, an expression is obtained for the quantity of gas released to the grain boundary, and this is compared with the analogous expression derived previously by Booth for the case where there are no intragranular traps. The fact that the resolution process through its effects on bubbles at the grain boundary will return some gas to the matrix and in so doing destroy the property of perfect-sink behavior is later considered. By an approximate method the appropriate modification to the formula describing the quantity of gas released to the boundary is deduced. This final expression, including the complete effects of intragranular trapping and irradiation-induced resolution on gas migration, may provide the basis on which to calculate the amount of gas which is eventually released external to the material from regions where intergranular bubbles grow so large that they interlink.