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The busyness of the nuclear fuel supply chain
Ken Petersenpresident@ans.org
With all that is happening in the industry these days, the nuclear fuel supply chain is still a hot topic. The Russian assault in Ukraine continues to upend the “where” and “how” of attaining nuclear fuel—and it has also motivated U.S. legislators to act.
Two years into the Russian war with Ukraine, things are different. The Inflation Reduction Act was passed in 2022, authorizing $700 million in funding to support production of high-assay low-enriched uranium in the United States. Meanwhile, the Department of Energy this January issued a $500 million request for proposals to stimulate new HALEU production. The Emergency National Security Supplemental Appropriations Act of 2024 includes $2.7 billion in funding for new uranium enrichment production. This funding was diverted from the Civil Nuclear Credits program and will only be released if there is a ban on importing Russian uranium into the United States—which could happen by the time this column is published, as legislation that bans Russian uranium has passed the House as of this writing and is headed for the Senate. Also being considered is legislation that would sanction Russian uranium. Alternatively, the Biden-Harris administration may choose to ban Russian uranium without legislation in order to obtain access to the $2.7 billion in funding.
W. H. Martin, D. M. Clare
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 468-473
Technical Paper | doi.org/10.13182/NSE64-A18765
Articles are hosted by Taylor and Francis Online.
Fast-neutron dose measurement by the activation of nickel foils involves a correction for thermal-neutron burnup of Co58, the daughter product of the (n,p) reaction. Fast-neutron irradiation of nickel produces Co58 in its ground and excited isomeric states, and recently the isomer has been shown to have a high thermal-neutron-absorption cross section. This paper considers how the determination of fast-neutron dose by nickel activation should be corrected for thermal-neutron burn-up of both ground and isomeric states of Co58. Results, which have been fully corrected, are compared with results obtained at low reactor power where the thermal-neutron burn-up of Co58 and Co58m is negligible. All the data considered were obtained from foils irradiated in rigs in hollow fuel elements in reactors of the DIDO type. The data demonstrate that accurate fast-neutron dose measurements, using nickel activation, in high-flux facilities can only be made if the thermal-neutron cross sections of Co58 and Co58 m and the branching ratio of the Ni58 (n,p) reaction have previously been determined in the neutron spectrum being utilised.
