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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
X. B. Zheng, M. Matsuyama, Y. R. Niu, Yi Zeng, H. Ji, L. P. Huang
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 46-49
Hydrogen/Tritium Behavior | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14110
Articles are hosted by Taylor and Francis Online.
Tungsten (W) and boron carbide (B4C) coatings deposited on metallic substrates have received considerable attention in recent years because of their potential application in nuclear fusion devices, especially as plasma facing materials (PFMs). In the present study, W and B4C coatings have been deposited by vacuum plasma spraying technology. The tritium retention behaviors of the W and B4C coatings were investigated and comparatively studied by using -ray-induced X-ray spectrometry (BIXS). The effects of tritium exposure temperature were examined as well. The obtained results showed that much stronger X-ray peaks of Ar(K) appeared in the BIXS spectra for the B4C coatings as compared with those for the W coatings, indicating of higher tritium absorbability for the B4C coatings owing to large amount of micro-pores in the coatings. After exposed to tritium gas at 923 K, significantly enhanced tritium retentions were detected for both the W and B4C coatings as compared with those exposed at 573 K.
