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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.”
Zachary S. Hartwig, Massimo Zucchetti
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 725-729
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12471
Articles are hosted by Taylor and Francis Online.
A critical aspect of the design of a tokamak-based neutron source is to ensure that radiation limits of the structural and magnet-insulating materials are not approached during the lifetime of the tokamak. To this end, we present an exploratory neutronics study of a materials testing facility that is based on Ignitor, a high-field tokamak. It shown that sufficient radiation damage to test materials located in the Ignitor first wall can be obtained by sustaining a reaction rate of 3.33×1019 neutrons per second for 7 operational months. Solutions to mitigate terminal damage to the toroidal field coil insulators, including its substitution for modern radiation-resistant insulators and the use of advanced radiation shield materials, are explored, and their implication for the design of the facility is discussed.
