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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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.
R. E. Leuze, R. D. Baybarz, Boyd Weaver
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 252-258
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28887
Articles are hosted by Taylor and Francis Online.
The Tramex process, in which trivalent actinides are extracted into tertiary amine hydrochloride from concentrated lithium chloride solution, has been developed for isolation of transplutonium elements from irradiated High Flux Isotope Reactor targets. Tests made in laboratory scale mixer-settlers gave americium losses of about 0.01 % and fission product decontamination factors of equal to or greater than 104. Nickel was the only contaminant that followed the transplutonium elements through the Tramex process. No serious radiation induced effects were noted in 1- to 10-ml batch extraction tests at activity levels up to the proposed processing level of 10 w/liter. A process was developed for splitting transplutonium elements into two fractions. Transcurium elements are extracted into mono-2-ethyl-hexyl phenyl phosphonic acid from dilute hydrochloric acid while americium-curium and nickel contaminant from the Tramex process remain in the aqueous phase. Demonstration in a 10-ml batch countercurrent extraction with simulated feed containing tracers gave a californium loss of about 0.1% and an americium decontamination factor of 103. Important variables for both extraction processes are discussed.