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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 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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Fusion Science and Technology
Latest News
U.K., Japan to extend decommissioning partnership
The U.K.’s Sellafield Ltd. and Japan’s Tokyo Electric Power Company have pledge to continue to work together for up to an additional 10 years, extending a cooperative agreement begun in 2014 following the 2011 tsunami that resulted in the irreparable damage of TEPCO’s Fukushima Daiichi plant.
Wei Zhao, Yali Wang, Yuzhong Jin, Li Zhao, Hongxia Zhou, Lin Nie, Guangwu Zhong, Chunjia Liu, Christopher Watts, James Paul Gunn
Fusion Science and Technology | Volume 76 | Number 2 | February 2020 | Pages 79-87
Technical Paper | doi.org/10.1080/15361055.2019.1674123
Articles are hosted by Taylor and Francis Online.
The primary aim of the ITER divertor Langmuir probe system is to measure the plasma parameters at the divertor target plates. Saturation ion flux coming from the direct-current biased probe mode is used for advanced machine control, and the swept double-probe mode is recommended to measure electron temperature and density for physics studies. The design of the probe system includes three parts. First, tungsten Langmuir probes are mounted on the side of the target plates for collecting current from plasma, and thermomechanical simulation results show the design of the probe is robust and can survive under harsh working environments. Second, the electronics consists of the power supply, mode switching, and signal conditioning box and is used for driving Langmuir probes in different operation modes to obtain expected plasma information. Third, the functions of instrument and control include publishing configuration; monitoring and control; calibration; data acquisition; communication with the control, data access and communication (CODAC) system; and real-time ion flux measurement at the divertor target. The system design also complies with ITER’s technical practices, standards, and codes.