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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.
Hans K. Fauske
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE63-A17204
Articles are hosted by Taylor and Francis Online.
Critical two-phase, steam - water flows have been measured in horizontal test sections with pipe diameters of 0.125 and 0.269 in. internal diameter (i.d.) over a range of qualities from 0.01 to 0.7, mass velocities from 500 to 4200 lb/sec-ft2, and critical pressures from 40 to 360 lb /in.2 absolute. The critical flow data and a theory for the critical flow phenomena have been discussed (1, 2). In this paper an analysis for the pressure drop data in the approach region to critical flow is presented. The flow mixture accelerates to critical flow at the end of the test sections, and thus the pressure drop data are for flow regimes in which both momentum and frictional losses are important. By utilizing the model developed for estimating critical discharge rates (1), two-phase friction factors were calculated from the experimental data. The friction factors obtained correlated well in terms of the two-phase quality and appear to be independent of flow rate, static pressure, and test geometry for the conditions examined.