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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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Alexander S. Khapov, Sergey K. Grishechkin, Vladimir G. Kiselev
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 412-415
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T41
Articles are hosted by Taylor and Francis Online.
Tritium permeation through structural materials is a key issue in many activities linked with tritium handling both for radiological safety and accountancy reasons to say nothing of economical aspect: tritium is not the cheapest material in the world. It is widely recognized that ceramic coatings provide an attractive solution to lower tritium permeation in structural materials. Alumina based ceramic coatings have the highest permeation reduction factor for hydrogen. Nevertheless even small cracking will significantly spoil the permeation reduction factor of a protecting coating. Nowadays for hydrogenating neutron tube targets with tritium “VNIIA” uses working chambers manufactured by pressing of alumina based ceramics. These chambers have revealed extremely low hydrogen permeation upon conditions of their application. For this reason an attempt was made to apply low porous ceramics as a structural material of a bed body for tritium storage in a setup used for hydrogenating neutron tube targets at “VNIIA”. The present article introduces the design of the bed. This bed possesses essentially less hydrogen permeation factor than traditionally used beds with stainless steel body. Bed heating in order to recover hydrogen from the bed is suggested to be implemented by high frequency induction means. Inductive heating allows decreasing the time necessary for tritium release from the bed as well as power consumption. Both of these factors mean less thermal power release into glove box where a setup for tritium handling is installed and thus causes fewer problems with pressure regulations inside the glove box. Inductive heating allows raising tritium sorbent material temperature up to melting point. The latter allows achieving nearly full tritium recovery.