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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.
G. Srikantiah
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 175-183
Technical Paper | doi.org/10.13182/NSE66-A18302
Articles are hosted by Taylor and Francis Online.
Methods of long-term reactivity control for plutonium-fueled D2O-moderated reactors that favor high conversion ratios are considered. One method uses annular gaps around the fuel elements that can be selectively filled with the D2O moderator. Reactivity compensations ranging from 8 to 15% can be achieved with gaps of 6 to 8-cm thickness and a corresponding reduction in conversion ratio of 3 to 5%. In the second method, depleted uranium sleeves that can be removed as required during long-term operation are utilized around fuel elements in annular regions of the reactor. Sleeves of only 0.2-cm thickness, around fuel elements in the central region of the reactor, provide reactivity compensations of up to 10% and actually increase the conversion ratio in the design studied. Average conversion ratios of about 0.90 are obtained in a large D2O-cooled and -moderated reactor using Zircaloy pressure tubes at fuel burnup of 104 MWd/t. The average conversion ratios would increase to about 0.97 if beryllium-based pressure tubes could be developed.