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September 8–11, 2025
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.”
Mei-Ya Wang, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 335-340
Technical Paper | doi.org/10.13182/NSE14-97
Articles are hosted by Taylor and Francis Online.
For further improvements on thermal efficiency and operation safety, reactor internal pumps, instead of conventional recirculation systems, are adopted in an advanced boiling water reactor (ABWR). With the novel design of internal circulation, the traveling path and pattern of the recirculated liquid coolant in an ABWR is actually different from that of the coolant in a conventional boiling water reactor. To ensure operation safety, optimization of the coolant chemistry in the primary coolant circuit (PCC) of a nuclear reactor is essential no matter what type or generation the reactor belongs to. For a better understanding of the water chemistry in an ABWR, such as the one being constructed in the northern part of Taiwan, and for safer operation of this ABWR, in this study we conducted a proactive, thorough water chemistry analysis prior to the completion of this reactor. A well-developed computer code was used to investigate the effectiveness of hydrogen water chemistry (HWC) on the redox species concentrations and electrochemical corrosion potential (ECP) behavior of components in the PCC of the Lungmen ABWR in Taiwan. Our analyses indicated that the effective oxidant concentrations at the top of the downcomer location would be expected to be >100 ppb at 0.5 ppm [H2]FW at the original rated power. While an effective ECP reduction at 0.4 ppm [H2]FW was observed at the downcomer outlet, a 2.0 ppm [H2]FW was not enough to reduce the ECP below the Ecrit at the upper plenum outlet. In summary, the effectiveness of HWC in the PCC of an ABWR is expected to vary from location to location and eventually from plant to plant due to different degrees of radiolysis and physical dimensions in different ABWRs.
