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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. Z. Akcasu, M. M. R. Williams
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 403-413
Technical Paper | doi.org/10.13182/NSE04-A2466
Articles are hosted by Taylor and Francis Online.
Statistical aspects of particle transport in spatially random media in one dimension are studied analytically using the dichotomic and the binomial binary random processes as two models for the spatial randomness in the particle density. The mean and the variance of the flux are expressed in terms of the moments <U(x)n> of the stochastic propagator U(x) = exp[-z(x)], where z(x) is the optical path length. The moments <U(x)n> are rigorously calculable with the above random processes. In the case of semi-infinite media, the calculations are carried out using the one-dimensional, one-speed transport equation. In finite media, one-speed diffusion theory is used to calculate the mean and variance of the flux within the slab. In particular, the statistics of the albedo and the exit current are investigated. The mean of the local reaction rates within the slab is also calculated.