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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.
R. T. Jacobs, J. A. Merrill
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 480-496
Technical Paper | doi.org/10.13182/NSE60-A25834
Articles are hosted by Taylor and Francis Online.
The comparative correlations of this report thoroughly demonstrate that significantly more precise equations for calculating burnout heat flux can be obtained by following the proposed “system-describing” concept, that if the independent, system-describing variables of a system are known, the burnout heat flux can be predicted. With this concept, the independent variable of inlet temperature has been used rather than the dependent variable of outlet subcooling or enthalpy. The same statistical (regression analysis) method of correlation was used for burnout data from several sources with both inlet temperature and outlet enthalpy so that the consistently better predictions using inlet temperature would not be attributed to using a different method of correlation. Due to the fact that Reactor technology and design no longer allow the engineer safety factor added upon safety factor, a decided advantage of the regression analysis correlation is that it is possible to calculate the statistical uncertainty of the predicted burnout heat flux.