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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
State legislation: Colorado redefines nuclear as “clean energy resource”
Colorado Gov. Jared Polis signed a bill into law on Monday that adds nuclear to the state’s clean energy portfolio—making nuclear power eligible for new sources of project financing at the state, county, and city levels.
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.