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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Dongxun Zhang, Wei Liu, Yuan Qian, Ji Que
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 681-684
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T109
Articles are hosted by Taylor and Francis Online.
Tritium was generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use Flibe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs would be an important safety issue because it could easily diffuse through high temperature heat exchangers into environment. The experimental technique of gas driven permeation was used to investigate the transport parameter of hydrogen in Hastelloy C-276 which was considered as one of the candidate structure materials. The measurements were carried out at the temperature range of 400-800°C with hydrogen loading pressures ranging from 5×103 to 4×104 Pa. The H diffusive transport parameters for Hastelloy C-276 followed an Arrhenius law in this temperature range and were decreased due to the existence of the alloying elements compared with Ni201. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to the slower dissociation process of H2 at the surface.