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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.”
Yoshiaki Oka, Hiroaki Wakabayashi, Shigehiro An, Ikunori Suzuki
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 287-296
Technical Paper | Reactor | doi.org/10.13182/NT76-A31665
Articles are hosted by Taylor and Francis Online.
Neutron streaming through the holes penetrating the grid-plate shield of a prototype liquid-metal fast breeder reactor was experimentally examined. The mockups of the grid-plate shield were made of iron and aluminum. Experiments were conducted in the vertical column of YAYOI, the fast-neutron source reactor at the University of Tokyo. A 3He spectrometer was employed to measure the transmitted neutron spectrum, while rhodium and indium threshold foils were used to determine the integral flux above specific energies and their spatial distributions in the form of reaction rates. The streaming factor for usual small bent holes is 1.28 ± 0.04 for the integral neutron flux above 0.1 MeV and 1.30 ± 0.12 for the reaction rate of the indium foil. Use was made of the one- and two-dimensional neutron transport codes ANISN and TWOTRAN for evaluation by computation. The reaction rates calculated by an infinite slab model with the ANISN code agree well with the experiments when normalized at the source point where neutrons are incident on the grid-plate shield.
