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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
Standards Program
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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Latest News
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. G. Gaul, W. L. Pearl
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 30-41
Technical Paper | doi.org/10.13182/NSE63-A17207
Articles are hosted by Taylor and Francis Online.
Type 304 stainless steel cladding material has been corrosion tested under heat transfer conditions at metal temperatures up to 1300°F in specially constructed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam have been controlled to simulate that found in boiling water reactor type systems. Good corrosion resistance and low metal release to system up to metal temperatures of 1100°F were experienced with an expected pattern of an initially high corrosion rate that decreased to a lower constant rate with time up to 4500 hr. A compositionally disturbed layer developed adjacent to the scale in the 1100°F to 1300°F metal temperature range on the heat transfer specimens. The layer continued to grow with time but had little effect on the corrosion rate within the 2500 hours of testing.