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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Y. Asakura et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 401-404
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A953
Articles are hosted by Taylor and Francis Online.
In order to realize the deuterium plasma experiments by using the Large Helical Device (LHD), NIFS is planning to install the system for tritium recovery from exhaust gas and effluent liquid. With the case of adopting generally used tritium recovery systems, NIFS has also made the development plans for the compact and less waste generating recovery system by applying the latest technologies such as tritium gas extraction with a proton conducting ceramic and tritiated water vapor removal with a membrane type dehumidifier. Applicability of these new technologies on the tritium recovery system for the LHD deuterium plasma experiment are evaluated quantitatively using the latest experimental data.Mock-up tests of the membrane type dehumidifier are carried out and verified the way of automated operation and stable dehumidifier performance during a long time operation.
