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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.
A. M. Melandri, F. Premuda, G. P. Prelati
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 225-233
Technical Note | doi.org/10.13182/NSE74-A28209
Articles are hosted by Taylor and Francis Online.
Calculations of neutron escape probability from a homogeneous isotropically scattering slab of finite optical thickness are reported as obtained by solving exactly the stationary linear integral transport equation for the total flux of monoenergetic neutrons. This is done for both critical and subcritical configurations of the slab under examination, with both constant and variable sources being referred to in the latter configuration. Due to the transport approach here used, the numerical results for the escape probability cover the full range of variation of the mean number of scattered neutrons per collision, cs, i.e., 0 ≤ cs ≤ 1, whereas the half-thickness of the slab considered ranges from 5 or 10 mean-free-paths down to values as small as 10-4 mean-free-paths.