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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.
George H. Miley
Nuclear Science and Engineering | Volume 21 | Number 3 | March 1965 | Pages 357-368
Technical Paper | doi.org/10.13182/NSE65-A20039
Articles are hosted by Taylor and Francis Online.
An asymptotic velocity of (18.79 ± 0.32) × 103 cm/sec is reported for the propagation of a TRIGA reactor neutron pulse through a 4 ft × 4 ft × 5.8 ft graphite thermal column. Interpretation in terms of a proposed theory yields Dv = (2.34 ± 0.02) × 105cm2/sec for 1.60 g/cm3 graphite. The propagation velocity was found to be independent of reactivity inserted in the range covered by experiment (to 2.90 dollars). Also, the pulse shape was preserved with an amplitude attenuation length equal to that for the steady-state thermal flux. These results are attributed to the fact that the neutron lifetime in the column was shorter than the pulse width and period. Calculations are presented for the reverse situation where the pulse shape is distorted. Pulse measurements with a Boral curtain lowered into the column are used to test the theory for situations where the slowing-down density is important.