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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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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.
Teruya Tanaka, Hiroyuki Noto, Fuminobu Sato, Yoshimitsu Hishinuma, Hiroyuki A. Sakaue, Masahito Yoshino
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1076-1083
Technical Paper | doi.org/10.1080/15361055.2019.1658039
Articles are hosted by Taylor and Francis Online.
To examine the impact of nuclear transmutation in K-type and N-type thermocouples on temperature measurements in a fusion reactor, thermocouples with altered compositions were fabricated, and their responses were obtained at up to 800°C. The compositions of the thermocouples were altered according to transmutation calculations simulating the 3.5-, 4.6-, and 7-year use at the first wall and 40-year use at the front surface of the radiation shield. Comparison of the responses with commercial thermocouples at 800°C showed that the K-type and N-type thermocouples with altered composition simulating the 7-year use at the first wall indicate 20% to 25% lower temperatures. In this condition, the weight ratio of additive powders for simulation of transmuted elements was ~3%. The differences of responses between the commercial thermocouples and thermocouples simulating transmutation are dependent on the weight ratio of the additive powders. The present data could be used for estimation of response degradation of thermocouples used for long-term operation in a fusion reactor.