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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.
