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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.
James Y. N. Wang
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 18-30
Technical Paper | doi.org/10.13182/NSE64-A18138
Articles are hosted by Taylor and Francis Online.
Titanium and titanium alloys are not generally resistant to mercury in the temperature range between 371 to 538 C. The extent of corrosion is dependent upon alloy composition and heat treatment. Nitrided surfaces of titanium and its alloys exhibit high resistance to mercury at 538 C for periods up to 14 days. At this temperature, mercury vapor attacks certain nitrided alloys while others are immune. For instance, the corrosion of a nitrided Ti/8wt% alloy was found to be insignificant; however, severe corrosion occurs at the nitrided layer of Ti/7wt% Al/12wt% Zr.a A study of the effect of metallic additives to mercury on the corrosion resistance of titanium at 538 C has also been made. It has been shown that a saturated mercury solution of zirconium or nickel exerts a strong influence in reducing corrosion. The films formed may act as a diffusion barrier between solid and liquid.