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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.
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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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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.
Jacques Chêne
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 506-509
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1864
Articles are hosted by Taylor and Francis Online.
Hydrogen deformation interactions are known to control the environmental degradation effects (H and 3He embrittlement, stress corrosion cracking,...) associated with the presence of H and its isotopes in structural materials. Different types of interaction have been investigated : trapping on stress field and strain-induced defects, enhanced diffusion along dislocation networks, transport by moving dislocation. For several reasons, the quantification of these interactions is a major challenge in nuclear systems involving the presence of tritium : prevention of tritium-induced damage, tritium inventory, management of tritiated waste...This paper reports recent results on the quantitative characterization of tritium deformation interactions in fcc materials.