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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
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.