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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Yudai Urabe, Kenichi Hashizume, Teppei Otsuka, Kan Sakamoto
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 392-397
Technical Paper | doi.org/10.1080/15361055.2020.1712992
Articles are hosted by Taylor and Francis Online.
Tritium permeability through FeCrAl-oxide-dispersion-strengthened (ODS) ferritic steel containing Ce oxides (Ce-ODS steel) was measured at temperatures ranging from 373 to 623 K. Some of the Ce-ODS steel specimens were oxidized by means of an autoclave treatment at 563 K for 30 days to examine the effect of the surface oxidized layer on the tritium permeability. The tritium permeability obtained for nonoxidized specimen was consistent with that for other common ferritic steels and FeCrAl ferritic steel. For the oxidized specimen, the surface oxide layer suppressed the apparent tritium permeability. The permeability for the oxidized specimen also depended on the atmosphere of the downstream in the permeation experiment: An atmosphere containing water vapor yielded lower tritium permeability compared with a reductive one.
