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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Song Jiangfeng, Huang Guoqiang, Huang Zhiyong, Chen Chang’an, Luo Deli
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 576-579
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T83
Articles are hosted by Taylor and Francis Online.
Tritium is a fuel and the most mobile and significant radioactive sources for ITER. In the design of TBM tritium systems of China, the safety design of common chemistry engineering system and tritium safety design are considered at the same time. It is necessary to avoid a continuous increase of the tritium concentration in the coolant and to reduce the tritium permeation into the secondary coolant as well as environment. In this paper, the design and tritium permeation analysis of China HCCB TBM port cell are introduced. At first, the primary design considerations of the system are given to fulfill the engineering demand of the ordinary system (non radioactive system). Then the tritium permeation, the release analysis, the effect of tritium release to the people and environment are discussed. From the calculation of the tritium permeation in the systems housed in the port cell, tritium permeation barrier is needed in the higher temperature components such as the reduction bed and the heater.