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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.”
J. M. Ryskamp, D. R. Harris, M. Becker
Nuclear Science and Engineering | Volume 77 | Number 3 | March 1981 | Pages 285-296
Technical Paper | doi.org/10.13182/NSE81-A19839
Articles are hosted by Taylor and Francis Online.
The sensitivity of light water reactor (LWR) fuel cycle parameters and costs to uncertainties in thermal nuclear data and methods is examined using a code package developed at Rensselaer Polytechnic Institute. Cross sections averaged over the thermal energy (<1- or 2-eV) group are shown to have an important economic role for LWRs. When it has been determined that fuel cycle parameters and costs are sensitive to a specific thermal group cross section, it becomes desirable to determine how specific energy-dependent cross sections influence fuel cycle parameters and costs. The FASTT code was written to compute detailed sensitivity coefficients using either a direct or a perturbation technique. Multigroup cross-section sensitivity coefficients vary with fuel exposure. After computing the changed exposure-dependent thermal group cross section, new fuel cycle parameters and costs are computed by a sequence of fuel depletion, core analysis, and cost codes. One can therefore obtain the change in fuel cycle cost for different fuel cycle options induced by a change in the shape of a detailed thermal cross section. A striking feature of our thermal analyses is the (usually) overwhelming importance of the hardened Maxwellian energy region (0.01 to 0.1 eV). The FASTT code is also used to determine the importance of the frequency distribution used to compute neutron scattering kernels based on the incoherent approximation. The sensitivities to Nelkin's scattering data are not large. A method, having potentially large implications for LWR design, is developed for obtaining correspondence among different scattering kernels.