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August 24–27, 2026
Dallas, TX|Hilton Anatole
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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.
H. L. Dodds, Jr., J. C. Robinson, A. R. Buhl
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 262-274
Technical Paper | doi.org/10.13182/NSE72-A22413
Articles are hosted by Taylor and Francis Online.
A transfer and scattering matrix technique is used to solve one-dimensional, time-dependent, multigroup, discrete ordinates equations and those including the delayed-neutron equations. The solution is obtained in the frequency domain as a distributed parameter transfer function. This technique can accomodate anisotropic, spatially distributed extraneous sources and general anisotropic scattering. The numerical problems associated with the technique are analyzed, and a procedure is presented for controlling them. The results obtained with this technique are in good agreement with (a) statics results obtained from standard discrete ordinates calculations, and (b) experimental kinetics noise data obtained from a critical fast assembly. Calculated results of a simulated pulsed-neutron experiment on a subcritical fast assembly are presented.