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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. Melese-d'Hospital
Nuclear Science and Engineering | Volume 35 | Number 2 | February 1969 | Pages 165-175
Technical Paper | doi.org/10.13182/NSE69-A21132
Articles are hosted by Taylor and Francis Online.
If the coolant mass flow were constant across the core, the coolant temperature rise would be proportional to the channel power. But, without orificing, the coolant mass flow in the hot channel is smaller than the average flow while the outlet temperature is hotter than the mixed mean temperature. The approximate radial distributions of coolant mass flow (M/M0) and temperature rise (ΔT/ΔT0) are shown to depend only upon the (arbitrary) radial flux distribution (H/H0) and upon a single lumped core parameter (δ), proportional to the product of the pressure by the pressure drop. For simple radial flux distributions and when δ goes from zero to infinity, (M0/Mav) increases approximately from (Hav/H0) to one, while (ΔT0/ΔTav) decreases approximately from (H0/Hav)2 to (H0/Hav). The relationships between hot channel parameters, maximum clad or fuel temperatures, and thermal power are derived in the Appendix for a “chopped cosine” axial flux distribution.
