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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. P. J. Hodgson, R. W. Grimes, M. J. D. Rushton, O. J. Marsden
Nuclear Science and Engineering | Volume 181 | Number 3 | November 2015 | Pages 302-309
Technical Paper | doi.org/10.13182/NSE14-156
Articles are hosted by Taylor and Francis Online.
Computational models provide a framework through which to predict impurity in-growth in reactor generated radiological sources. However, the energy group structure and methodology used in these codes can have a significant impact on the accuracy of neutron cross sections and, as a result, on the inventory values calculated. The European Activation SYstem II (EASY-II) partitions neutron data in a number of different standard structures and then uses these to generate energy collapsed cross sections for each neutron reaction of interest. How well these single values represent the true neutron environment of the reactor is key to the codes efficacy for evaluating source impurities for use in material attribution. By comparing EASY-II nuclide inventories for cobalt source materials against analytically derived equivalents, these approximations have been shown to have limited impact. However, of the fission applicable standard structures investigated, only XMAS and CCFE were capable of precisely accounting for the differences in the energies required to simulate all the neutron reactions of potential interest to forensic investigations.