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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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
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.
