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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.”
Koji Oishi, Yujiro Ikeda, Chikara Konno, Tomoo Nakamura
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 291-309
Technical Paper | Shielding | doi.org/10.13182/FST90-A29301
Articles are hosted by Taylor and Francis Online.
The principal components of concrete were irradiated by 14-MeV neutrons for measurement of their induced activities to verify the activation calculation code THIDA-2 and its related cross-section library CROSSLIB. The observed radioactive nuclides, whose half-lives range from minutes to years, were 28Al, 29Al, 27Mg, 44K, 41Ar, 56Mn, 42K, 24Na, 43K, 48Sc, 47Sc, 47Ca, 46Sc, 54Mn, and 22Na, Experimental and calculated results were compared. Good agreement was obtained within ±20%, for 28Al, 56Mn, 42K, 24Na, 48Sc, 47Ca, 46Sc, and 54Mn with well-estimated production cross sections. Large differences were also observed, however, ranging in value from −50 to +100%, for the other nuclides. The cross-section values near 14 MeV for these nuclides were replaced with the cross-section data measured at the Fusion Neutronics Source at the Japan Atomic Energy Research Institute. Recalculation was performed using the newly estimated group cross sections derived from these data, and agreement between experiment and calculation was improved to within ±20%. From this experimental study, it was proved that the uncertainties of the activation cross-section values could satisfactorily explain the discrepancies of the induced activity calculation.
