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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
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.