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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.
A. Chesné, G. Koehly, A. Bathellier
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 557-565
Technical Paper | doi.org/10.13182/NSE63-A18448
Articles are hosted by Taylor and Francis Online.
Trilaurylamine nitrate diluted in dodecane is considered as an extracting agent for plutonium. The use of this solvent is proposed for a tail-end plutonium recovery from irradiated uranium solutions which have already been purified by one or more TBP cycles. Mention is made of general properties of the solvent. The study of the stripping of plutonium is emphasized. The first choice stripping solution is a mixture of sulfuric and nitric acid which gives a final concentrated and purified Pu4+ solution. Some alternative purification flowsheets are given. They show that a decontamination factor of 104 can be attained for Zr-Nb and uranium. Kinetics of the extraction and radiolytic degradation of the solvent are briefly discussed.
