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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.
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 81-88
Technical Paper | doi.org/10.13182/NSE70-A19330
Articles are hosted by Taylor and Francis Online.
The findings of a theoretical study of heat transfer for laminar, in-line flow through unbaffled rod bundles are reported. The results of a numerical solution are given for equilateral triangular bundles, for P/D ratios ranging from 1.001 to 2.00, for fully developed temperature profiles, and for the thermal boundary conditions of uniform wall heat flux in all directions. They are given in terms of rod-average heat transfer coefficients and circumferential variations of the wall temperature. The rod-average heat transfer coefficient goes through a rather sharp maximum as the P/D ratio is varied, the maximum occurring at P/D = 1.20. The circumferential variation of the wall temperature, large at small P/D ratios, decreases as P/D is increased, until at P/D > ∼ 1.50 it is negligible. Results calculated for the thermal boundary conditions of uniform wall heat flux in the axial direction and uniform wall temperature in the circumferential direction agreed excellently with previous results, attesting to the accuracy of the present calculational method.