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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.”
J. Tommasi, G. Noguere
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 232-241
Technical Paper | doi.org/10.13182/NSE160-232
Articles are hosted by Taylor and Francis Online.
The PROFIL and PROFIL-2 experiments, performed in the Phénix demonstration fast reactor, irradiated 130 small separate samples containing almost pure isotopes. These highly accurate experiments are a very specific and powerful source of information on the nuclear data of major and minor actinides and several fission products. Their analysis is carried out using the ERANOS-2.1 code system associated to JEFF-3.1 cross-section, fission yield, and decay data. The consistency of the results demonstrates the overall good quality of the actinide nuclear data and experimental techniques used and points out where specific improvement is necessary: fission yields of 235U on neodymium isotopes (5% bias) and integral capture cross sections of the actinides 232Th, 234U, 242Pu, 244Cm, 246Cm (more than 10% bias), 233U, 237Np, 241Pu, and 243Am (bias between 5 and 10%). The optimal values of the branching ratios for 241Am capture (0.85 on 242gAm and 0.15 on 242mAm) are consistent with the latest evaluation data in the fast neutron range. A similar analysis characterized the degree of accuracy of the integral capture cross sections of 19 fission products. Two new experiments of the same kind have been irradiated in Phénix and will undergo dissolutions and isotopic analyses. When they are completed, the analysis of the results will provide additional useful data in both a standard and a slightly moderated neutron spectrum.
