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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.”
D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 521-533
Technical Paper | doi.org/10.13182/NSE76-A14488
Articles are hosted by Taylor and Francis Online.
A fast-neutron time-of-flight spectrometer has been constructed for the purpose of measuring neutron differential cross sections of interest to the controlled thermonuclear reactor (CTR) program. The experimental facility provides the capability of measuring scattering cross sections of a few mb/sr to ∼5% absolute accuracy in the energy range from 6 to 15 MeV. Source neutrons are provided by the D(d,n)3He reaction. Scattered neutrons are detected at 28 angles between 25 and 160 deg in a massively shielded NE218 liquid scintillator located 4 m from the scattering sample. Absolute cross sections are obtained by normalizing to n-p scattering. Differential elastic and inelastic scattering cross sections are reported for 8.97-, 9.19-, 9.55-, 9.96-, 10.21-, 10.69-, 10.96-, 11.16-, 11.73-, 11.96-, 12.44-, 12.95-, 13.95-, 14.43-, and 14.93- MeV neutrons incident upon high-purity carbon. Monte Carlo simulation has been used to correct for finite source and sample effects. These data partially fill the 9- to 15-MeV gap in the carbon elastic and inelastic scattering data set required for the CTR program.