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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.”
Hideo Matsuzuru, Noboru Moriyama
Nuclear Science and Engineering | Volume 80 | Number 1 | January 1982 | Pages 14-25
Technical Paper | doi.org/10.13182/NSE82-A21400
Articles are hosted by Taylor and Francis Online.
The leaching behavior of a cement composite incorporating evaporator concentrates produced at a pressurized water reactor nuclear power plant has been studied for safety assessment of the final disposal of waste solids. Leaching tests were carried out in accordance with the method recommended by the International Atomic Energy Agency. Amounts leached were measured as functions of the waste-cement weight ratio (Wa/C), temperature of leachant, and curing time of specimens. The solidification of wastes containing boric acid with cement-vermiculite mixture was much improved by the alkalinization of the waste up to pH 12. The fraction of 3H or 90Sr leached increases with increasing Wa/C and leachant temperature, and with decreasing curing time. The amount of either 137Cs, 60Co, or 144Ce leached does not depend much on Wa/C, but depends on the leachant temperature and curing time. The leaching fraction for these nuclides in de-ionized water as a leachant is higher than that in the synthetic seawater. The leachabilities of nuclides follow the order: 3H > 137Cs > 90Sr > 60Co > 144Ce. The relationship between the fraction leached and the ratio of surface area and volume of a specimen has been examined in order to estimate the amounts leached from specimens of various geometries. On the basis of the results obtained, estimations were made of the amounts leached from a 200-ℓ composite volume that is exposed to a water environment for extended periods.
