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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Makoto Oyaidzu, Masayuki Ohta, Kentaro Ochiai, Atsushi Kasugai
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 842-847
Technical Paper | doi.org/10.1080/15361055.2021.1962119
Articles are hosted by Taylor and Francis Online.
In the Advanced Fusion Neutron Source (A-FNS), an accelerator-driven fusion-relevant neutron source that is planned for development in Japan, a few grams (3.5 g at full power operation) of tritium will be generated every year, mainly in the lithium target system. Since the generated tritium would migrate out of the lithium target system, it is necessary to estimate the tritium migration into and out of the lithium target system for the design of detritiation systems for the A-FNS. Therefore, a preliminary estimation is performed in the present study. As a result, it is found that almost all of the generated tritium in the lithium target system would be trapped in the impurity removal system, while less than 0.5% would migrate out. It is also indicated that the amount of tritium that would migrate out of the lithium target system would be able to be processed with the existing techniques so far.
