ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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.
Y. Kosaku, Y. Yanagi, M. Enoeda, M. Akiba
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 958-961
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22727
Articles are hosted by Taylor and Francis Online.
As a part of design study of candidate DEMO blanket in Japan, evaluations of tritium permeation in solid breeder blankets cooled by supercritical water was performed. The evaluations were performed under detail design of the blankets with nuclear and thermal analyses. F82H was selected as the structural material and the temperature of cooling tubes in the tritium breeder zone was evaluated between 673K and 783K. In this temperature range, tritium permeation rate through the cooling tubes in tritium breeder zone was evaluated and also tritium permeation into the first wall cooling water by the implantation of tritium particle was evaluated. In addition, requirements for preventing tritium permeation into the cooling water have been examined.