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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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Fusion Science and Technology
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Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
Norihiro Ikemoto, Hironori Shiraishi, Akira Tsuguchi, Mutsumi Nakamura, Naoki Mizuniwa, Satoshi Akamaru, Masanori Hara
Fusion Science and Technology | Volume 81 | Number 6 | August 2025 | Pages 580-590
Regular Research Article | doi.org/10.1080/15361055.2025.2456894
Articles are hosted by Taylor and Francis Online.
A tritium removal system (TRS) has been designed and installed. The TRS can remove tritium leaked into a workspace (100 m3). The tritium removal process in the TRS is a wet method in which leaked tritium compounds are oxidized to tritiated water by a catalyst, and the tritiated water is captured by a molecular sieve bed. The tritium removal performance (TRP) of the TRS was evaluated using H2 and CH4. The TRP is expressed by the relationship between the tritium oxidation efficiency of the catalyst bed and the water-capturing efficiency of the molecular sieve bed. The oxidation efficiency of CH4 increased with increasing the catalyst temperature, and it reached to 0.75 around 280°C. The water-capturing efficiency was found to be 0.97 during the operation.
The relationship between the oxidation efficiency and the water-capturing efficiency was reconstructed to chart and evaluate the tritium removal time. The chart evaluating the TRP of the TRS satisfied the design requirements. The design and evaluation method of this TRS can be applied to other TRSs using the wet method.
