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Atlanta, GA|Atlanta Marriott Marquis
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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.”
E. R. Hodgson
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 89-96
Diagnostics | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14118
Articles are hosted by Taylor and Francis Online.
Present ITER diagnostics are designed to provide machine protection, basic and advanced control, fusion performance evaluation, and an extensive measurement capability for furthering plasma physics understanding. However, in the longer term beyond ITER, diagnostic components and associated materials must survive extended periods in the more hostile environment of not only DEMO, but also fusion power plants. In addition to the need to minimize penetrations in the first wall, undoubtedly due to their known high sensitivity to radiation, the use of insulators, and hence diagnostics, will be further severely restricted to those essential to operation, safety, and maintenance related to plasma control and machine protection. The problems we will have to address are related to long-term fluence or dose-related degradation of the required properties due to aggregation and segregation of radiation-induced defects and impurities present in the original materials, as well as H, He, and other transmutation elements. To resolve these challenges, long-term research activities must increase. For the diagnostics (and other systems), in situ irradiation testing is essential. In the near- to mid-term future, available experimental fission reactors will be invaluable, where even basic problems such as irradiation in vacuum and temperature control must be overcome.