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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Japan gets new U for enrichment as global power and fuel plans grow
President Trump is in Japan today, with a visit with new Prime Minister Sanae Takaichi on the agenda. Takaichi, who took office just last week as Japan’s first female prime minister, has already spoken in favor of nuclear energy and of accelerating the restart of Japan’s long-shuttered power reactors, as Reuters and others have reported. Much of the uranium to power those reactors will be enriched at Japan’s lone enrichment facility—part of Japan Nuclear Fuel Ltd.’s Rokkasho fuel complex—which accepted its first delivery of fresh uranium hexafluoride (UF₆) in 11 years earlier this month.
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.
