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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.”
N. J. Peters, J. C. McKibben, K. Kutikkad, W. H. Miller
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 210-219
Technical Paper | doi.org/10.13182/NSE10-71
Articles are hosted by Taylor and Francis Online.
A detailed study at the Missouri University Research Reactor indicates that limitations in the energy balance methodology, using the Monte Carlo N-Particle transport code (MCNP) and the Evaluated Nuclear Data Files (ENDF), affect the accuracy of predicting important parameters for reactor physics studies. In the case of fuel conversion, key parameters such as flux and power level cannot be measured until the converted reactor is operating. Therefore, predictions with well-known uncertainties are essential for an effective conversion. However, due to inherent energy balance problems in the isotopic heating evaluations for materials within various fuel matrices, in particular the U-10Mo monolithic fuel, the values for the predicted parameters could vary more than previously estimated. In particular, the total recoverable energy per fission, which directly affects the calculated flux for a given power level, appears to be underestimated by MCNP's energy balance method. Therefore, an alternative methodology for predicting the total recoverable energy of a system was investigated. Results for the proposed low-enriched uranium U-10Mo configuration show that there is a 3.02-MeV difference between the total recoverable energy per fission from this work and that from the MCNP predictions. A similar comparison for the present highly enriched uranium UAlx configuration shows a difference of 1.24 MeV.
