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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.”
Chenglong Wang, Yao Xiao, Jianjun Zhou, Dalin Zhang, Suizheng Qiu, Guanghui Su, Xiangzhou Cai, Naxiu Wang, Wei Guo
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 86-102
Technical Paper | doi.org/10.13182/NSE13-60
Articles are hosted by Taylor and Francis Online.
The fluoride salt–cooled high-temperature reactor (FHR), combining high-temperature graphite-matrix coated-particle fuel (TRISO) for high-temperature gas-cooled reactors and liquid salts developed for molten salt reactors with safety systems that originate from sodium fast reactors, is a new concept reactor. The thermal-hydraulic characteristics of the fluoride salt–cooled high-temperature test reactor (FHTR) are of great importance to the development of the FHR technology, which is mainly ongoing in both China and the United States. In this paper, the thermal hydraulics of the FHTR designed by Shanghai Institute of Applied Physics is studied in different power modes. The one-dimensional temperature distributions of the coolant and the fuel pebble are obtained using a steady-state thermal-hydraulic analysis code for FHR. The detailed local flow and heat transfer are investigated by computational fluid dynamics for the locations that may have the maximum pebble temperature based on the results of a single-channel model. Profiles for temperature, velocity, pressure, and Nusselt number of the coolant on the surface of a pebble as well as the temperature distribution of a fuel pebble are obtained and analyzed. Numerical results indicate that the results of the three-dimensional simulation are in reasonable agreement with those of the single-channel model with a maximum deviation of 17.9%. They also illustrate the safety operation of FHTR in different power modes. This study aims to provide useful information for experimental and mechanism research of FHRs.
