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Nuclear Energy Conference & Expo (NECX)
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.”
Nikolai Vododokhov, Kendall Erlandson, David R. Novog
Nuclear Science and Engineering | Volume 199 | Number 9 | September 2025 | Pages 1492-1511
Research Article | doi.org/10.1080/00295639.2025.2455353
Articles are hosted by Taylor and Francis Online.
Nuclear energy provides a low-carbon source of electricity that provides consistent and reliable power in a cost-effective manner. However, the accident at Fukushima Daiichi in 2011 demonstrated several important lessons on nuclear power plant severe events and risk mitigation and led to important changes in designs, improvement in emergency planning, and better understanding of external event hazards. Since 2011, the Fukushima accident has also led to new methodologies to characterize risk for low-probability events such as station blackout (SBO). In particular, large external events that lead to loss of Class IV power, and subsequent failures of backup power (Class III power) and or emergency power, and where the outcome may be dependent on human/emergency response functions, require additional methodological development to better quantify the risks and consequences. Dynamic Probabilistic Safety Assessment (D-PSA) is a set of stochastic tools that allows the integration of technology availability (e.g. as in standard Probabilistic Safety Assessment), human action probability, uncertainty in predictive models, and possible deviations in the timing of any automatic or human-initiated actions. It allows the analysis of accident consequences with different mitigation strategies and action timings and can include the evaluation of both safety (e.g. dose) and/or economic consequences. It can also be used as part of a larger risk informed methodology such as the Risk Informed Safety Margin Characterization approach proposed by the U.S. Light Water Reactor Sustainability (LWRS) Program to rank safety system and operator actions in terms of their probable impact on an event. The RAVEN framework developed under the LWRS Program is used as a D-PSA driver along with the TRACE thermal-hydraulic code to quantify risk evolution during transient event sequences. This paper uses the Dynamic Event Tree approach to analyze the critical time to failure for a SBO in a CANada Deuterium Uranium (CANDU) power plant and the impact of system reliabilities and timing on event outcomes.
