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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
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.
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.