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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
Jae-Uk Lee, Dong-you Chung, Hyun-goo Kang, Min Ho Chang, Pil-Kap Jung
Fusion Science and Technology | Volume 80 | Number 3 | May 2024 | Pages 582-589
Research Article | doi.org/10.1080/15361055.2023.2202302
Articles are hosted by Taylor and Francis Online.
In this study, the amount of 3He release from a tritium-loaded depleted uranium bed considering long-term operation in the fusion fuel cycle is assessed using empirical models. Several works are surveyed to investigate the trend of 3He released from uranium tritide. The model for 3He release is developed consisting of two parts, i.e., the natural release model and the heating release model, based on experimental studies. The natural release model is validated by applying it to experimental data. The model is applied to cyclic and long-term operation scenarios to assess the amount of 3He in the headspace of the metal tritide bed. The results show that the 3He release after long-term maintenance can be significant and must be separated from tritium before supply to the fuel cycle. During plasma operation and short maintenance, it is shown that the 3He release is less significant, but further requirement consideration is needed for the 3He separation process.
