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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
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
U.K., Japan step up progress toward fusion power demonstrations
Japan’s recent moves to boost fusion power in the nation’s energy plan and accelerate the timeline for a prototype fusion power plant come in response to increased global attention on fusion energy. Even as ITER faces delays, more than 40 private fusion developers are pursuing different technologies and competing for attention. And so are other countries, including the United Kingdom, which announced its plans for a fusion pilot plant back in 2019. Fusion companies and nations alike are responding to a growing sense that there is a race—or at least collective momentum—to commercialize fusion energy.
Y. Torikai et al.
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1057-1060
Contamination and Waste | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12598
Articles are hosted by Taylor and Francis Online.
A batch process concept for the decontamination from tritium of fusion reactor materials based on a hydrothermal treatment is under development at HRC. Essentially, tritium-loaded material is heated in a tightly closed vessel containing a defined amount of water. The objective of the water is to “capture” the released tritium in a small volume of liquid. For the detritiation, stainless steel temperatures in the range 393-473 K over a period of several days were found to be adequate. From the results it appears that by and large the released tritium accumulates in the purposely introduced water. The achieved degree of decontamination was estimated from the tritium concentration in the water and the tritium that remained in the decontaminated material. Tritium trapped in the surface layer of stainless steel was not reduced by the isochoric hydrothermal treatment in the same proportion as that in the bulk.