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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. Sun et al.
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 899-904
Tritium Storage | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12562
Articles are hosted by Taylor and Francis Online.
To efficiently confine the gaseous deuterium and tritium, which are the important fuels in the development of fusion energies, China has developed a series of hydrogen resistant stainless steels, named as the HR series of stainless steels. The mechanisms of the interactions between tritium with the decayed helium-3 and these stainless steels were investigated by theoretical calculations, experimental observations or tests through gaseous tritium loading into the stainless steels and years of storage. Results showed that the China made HR stainless steels had good performance to resist hydrogen damage or hydrogen embrittlement. They are the ideal structure materials for tritium systems used in a fusion reactor like ITER. Nevertheless, tritium permeation at high temperatures are still high. Tritium permeation barriers with the aluminides on the surface of the components were successfully developed, which could greatly reduce tritium permeation flux down to 2~3 orders of magnitudes.