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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.”
H. Plitz
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 48-58
Technical Paper | Fuel | doi.org/10.13182/NT78-A32090
Articles are hosted by Taylor and Francis Online.
Received December 21, 1976 Accepted for Publication September 7, 1977 Experience with continued operation of failed mixed-oxide fuel pins in liquid-metal-cooled reactors or in-pile sodium loops is available from a variety of beyond-fuel-failure experiments. The phenomena and effects on a large reactor system of continued beyond-fuel-failure operation are not well understood, but, except for the release and deposition of fission products and the chemical reaction of sodium coolant to oxide fuel, leading to pin swelling, no failure propagation due to continued operation of failed fuel pins has been observed. For economic reactor operation, further investigations are needed to establish a catalog of fuel failure types, sizes, and locations to describe the time-dependent effects of continued operation on reactor operation, shutdown requirements, instrumentation, surveillance, circuit systems, contamination, maintenance systems, and plant efficiency.
