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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. Marino
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 93-98
Technical Paper | doi.org/10.13182/NSE72-A22530
Articles are hosted by Taylor and Francis Online.
An analytical method is described which enables one to calculate the concentration profile of an interstitial solute of finite solubility in an alloy under a given thermal gradient. The method requires that one know beforehand the diffusion coefficient, the terminal solid solubility, and the heat of transport of the solute. The work is applied to the experimental conditions of Sawatzky and of Markowitz for hydrogen in Zircaloy. The agreement between the predicted profiles and the experimentally determined profiles is quite good for total concentrations less than ∼1000 ppm. For concentrations greater than this, some deviation is seen but the overall agreement is still considered good within the accuracy of the assumptions employed. The principles embodied in the analysis are easily generalized to include multidimensional thermal and concentration gradients.