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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.
F. W. Staub
Nuclear Science and Engineering | Volume 35 | Number 2 | February 1969 | Pages 190-199
Technical Paper | doi.org/10.13182/NSE69-A21134
Articles are hosted by Taylor and Francis Online.
Modeling of two-phase hydrodynamic phenomena with a refrigerant (Freon) has been carried out for several years because of the lower cost of experimentation with this working fluid. Freon-12a modeling of the critical-heat-flux condition, a coupled hydrodynamic thermal phenomenon, has recently been reported. The effort described here represents an extension of the critical-heat-flux modeling work using Freon-22.b A recently proposed correlation method, comparing Freon and water data, has been modified, and good agreement is shown between water and Freon-22 test results in a round tube with and without a twisted ribbon insert. The modeling technique is also extended to cover inlet subcooling and the operating pressure effect. In addition, some liquid-metal and water critical-heat-flux data are compared.