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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.
R. S. Booth, R. H. Hartley, R. B. Perez
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 404-414
Technical Paper | doi.org/10.13182/NSE67-A28955
Articles are hosted by Taylor and Francis Online.
A technique is presented for conducting neutron-wave experiments in thermal-neutron systems using either a sinusoidally modulated or a pulsed source of thermal neutrons. A neutron source suitable for this experiment is described, data-accumulation criteria are presented, and the electrical systems used for collection are discussed. A specific experiment with graphite is reported and the discussion of data analysis is carried through the experimental determination of this system's dispersion law. It is found that, in general, a pulsed source of thermal neutrons is more suitable for neutron-wave experimentation than a sinusoidally modulated source. Confirmation is given to the theoretical prediction that diffusion and thermalization parameters can be measured by this technique over a relatively wide range of frequency without significant higher space- and energy-mode contamination. The values we obtained for the diffusion and thermalization parameters for graphite of density 1.60 g/cm3 were α0 ± 91. ± 1 sec−1, D0 = (2.16 ± 0.01) × 105 (cm2 sec−1), C0 = (39. ± 2) × 105 (cm4 sec−1), and F0 = (12. ± 2) × 107 (cm6 sec−1).