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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.”
G. Verdú, R. Miró, A. M. Sánchez, O. Roselló, D. Ginestar, V. Vidal
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 256-269
Technical Paper | doi.org/10.13182/NSE04-A2456
Articles are hosted by Taylor and Francis Online.
The TRAC/BF1-VALKIN code is a new time domain analysis code for studying transients in a boiling water reactor. This code uses the best-estimate code TRAC/BF1 to give an account of the heat transfer and thermal-hydraulic processes and a three-dimensional neutronics module. This module has two options: the MODKIN option that makes use of a modal method based on the assumption that the neutronic flux can be approximately expanded in terms of the dominant lambda modes associated with a static configuration of the reactor core, and the NOKIN option that uses a one-step backward discretization of the neutron diffusion equation. To check the performance of the TRAC/BF1-VALKIN code, the Peach Bottom turbine trip transient has been simulated, because this transient is a dynamically complex event where neutron kinetics is coupled with thermal hydraulics in the reactor primary system, and reactor variables change very rapidly.
