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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
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.”
T. A. Gabriel, J. D. Amburgey, N. M. Greene
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 21-32
Technical Paper | doi.org/10.13182/NSE76-A28457
Articles are hosted by Taylor and Francis Online.
A data base of primary knock-on atom spectra and an analysis program have been created to assist experimentalists in studying, evaluating, and correlating radiation-damage effects in different neutron environments. Since experimentally obtained typical controlled thermonuclear reactor (CTR) neutron spectra are not presently available, the data base can be extremely useful in relating currently obtainable radiation damage to that anticipated in future fusion devices. However, the usefulness of the data base is not restricted to only CTR needs. Most of the elements of interest to the radiation-damage community and all neutron reactions of any significance for these elements have been processed, using available ENDF/B-IV cross-section data, and are included in the data base. Calculated data such as primary knock-on atom spectra, displacement rates, and gas production rates, obtained with the data base, for different radiation environments are presented and compared with previous calculations.
