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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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.
A. A. Yukhimchuk, A. S. Khapov, I. P. Maksimkin, V. V. Baluev, I. E. Boitsov, A. V. Vertey, S. K. Grishechkin, V. G. Kiselev, I. L. Malkov, R. K. Musyaev, V. V. Popov, D. T. Sitdikov
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 662-665
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T105
Articles are hosted by Taylor and Francis Online.
The article presents results of comparative tests for determination of deuterium fluxes permeating through walls of austenitic stainless steel AISI304 (DIN 1.4301) chamber and Al2O3 based ceramic F99.7 chamber. Both chambers represent a piece of Ø26x Ø22x117 mm3 tube with spherical bottom ending. It is shown that at 773 K and deuterium pressure of 1200 mbar the permeated deuterium flux through the stainless steel chamber constituted 8∙10-5cm3/s, while the flux through ceramic one it did not exceed the sensitivity of the measurement method threshold, namely ~1.5∙10-7cm3/s. The ceramic chamber turned out to survive more than 103 cycles of heating up to 773 K with no damages. It did not lose its impermeability up to 10 bar of internal deuterium pressure. The authors also present test results of a prototype bed for reversible tritium storage. The bed’s case was made of alumina based ceramic F99.7, titanium being used as tritide making metal and high frequency induction used for heating of tritide metal.