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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.”
Karl Hornyik
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 247-254
Technical Paper | doi.org/10.13182/NSE72-A22539
Articles are hosted by Taylor and Francis Online.
The generation of tritium from the 10B(n, 2α)3H reaction involving boric acid in the coolant-moderator of PWRs is studied. First, the total amount of tritium produced by this process during a core cycle is calculated for the case of base load operation assuming separability of the neutron flux into space, energy, and time modes as well as a linear decrease of the boric acid concentration in compensation for burnup effects. Subsequently, analytic solutions to this problem are obtained for square-wave load-following assuming both total and one particular mode of partial compensation of the reactivity transients due to xenon poisoning by boric acid. The limitation to load following due to practical limitation of the dilution rate is observed. The solutions are expressed in terms of commonly available plant parameters and are presented in graphical form as a function of characteristics of the load following program. The significance of the analysis is illustrated by means of a numerical example; details of the xenon-transient analysis are included as an appendix.
