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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.”
A. Charlier, M. Doucet, C. Vandenberg, W. de Roovere, J. Bens
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 451-457
Technical Paper | doi.org/10.13182/NSE88-A23578
Articles are hosted by Taylor and Francis Online.
For optimal operation of a power plant, it is now necessary to install an expert system in the control room, particularly to aid the operator in predicting, following, and explaining operating events. The three-dimensional MICROLUX code, foreseen for such a system, was tested on an operating event occurring in the Doel-3 reactor. After an ≈6-h scram, the return to full power (PN) was limited at 15% PN because of an unacceptable axial offset deviation, which was believed to have been caused by xenon buildup during the shutdown. The reactor was then required to be operated at reduced power for 18 h before again reaching nominal power. From the study, however, it seems that there was no danger in returning directly to full power in spite of the ex-core indications. The three-dimensional calculations and the ex-core results show that there is a need to investigate the ex-core/in-core relationship when the reactor is operated outside the calibration field. These preliminary results indicate that the axial offset concept should be analyzed on the basis of a large number of transient operating conditions with the help of three-dimensional methods, which give a better description of the core behavior during transients. The use of such methods could contribute to a safer and more economical operation of the reactor.