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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.
J. Chernick, S. Oleksa Moore
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 537-544
doi.org/10.13182/NSE59-A15516
Articles are hosted by Taylor and Francis Online.
The breeding potential of thermal reactors is re-evaluated on the basis of present nuclear data. It is concluded that positive breeding on the U233, thorium cycle is possible with a variety of moderators including heavy water, graphite, beryllium, and ordinary water. Current measurements indicate that the accepted thermal value of η23 = 2.28 ± 0.02 is somewhat conservative. Neutron spectrum considerations show that η23 decreases gradually with increasing resonance absorption to a minimum of 2.14 ± 0.04. When neutron losses to the moderator are considered, maximum breeding gains of 0.26, 0.22, 0.21, and 0.19, respectively, are obtained for D2O, graphite, Be, and H2O moderated reactors. The breeding gain in reactors partially or completely moderated by beryllium can be considerably increased if use is made of the fast effect, presently estimated at 1.075 ± 0.02 for pure beryllium. Probable breeding gains in proposed full-scale fluid fuel breeders are estimated at 0.09 for the Aqueous Homogenous Reactor and 0.05 for the graphite moderated Liquid Metal Fuel Reactor and Molten Salt Reactor. Breeding in predominantly thermal, solid fuel reactors also appears within reach if neutron losses are minimized. The possibility of positive breeding in near thermal, plutonium fuelled reactors is unsettled although this goal can be approached by maximum use of the fast effect in U238. Estimates of breeding ratios in plutonium fuelled reactors depends on the variation of η49 with neutron temperature which is still inadequately known.