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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.
Harshavardhan Kadvekar, Sana Khan, Sangeetha Prasanna Ram, Jayalekshmi Nair, S. Ganesan
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 356-370
Technical Paper | doi.org/10.13182/NSE15-103
Articles are hosted by Taylor and Francis Online.
In a majority of the cases, error propagation studies in nuclear science and engineering use the sandwich formula, which is strictly applicable when the probability density function of the random input quantities (e.g., the basic cross-section data) are determined completely by the mean and covariances. The use of the sandwich formula, which is also referred to in the literature as traditional first-order sensitivity analysis or adjoint-based sensitivity and uncertainty analysis, requires the assumption of linearity assumption and relatively small errors. For the first time, this paper examines the application of unscented transformation (UT) technique, which is used in control and reliability engineering, to error propagation in the nuclear field for nonlinear cases. Using different examples, this paper shows that this deterministic method of UT produces better results compared to the conventional sandwich formula for error propagation. An example on error propagation given in the literature is revisited, and a calculation of the efficiency of a gamma-ray detector is also presented for illustrative purposes using the UT method.