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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.”
Workshop
Thursday, April 8, 2021|11:45AM–1:00PM EDT
Session Chair:
Agustin Abarca
Alternate Chair:
Maria N. Avramova
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producers:
Jacob Weinberg (NCSU)
This workshop gives an overview of the advanced thermal-hydraulic sub-channel code CTF and its nuclear fuel rod solver CTFFuel. The code is used for steady state and transient design and safety analyses of current and advanced nuclear reactors. CTF is also the thermal-hydraulic component of the CASL-developed Virtual Environment for Reactor Applications (VERA) core simulator used for thermal feedback and prediction of thermal-hydraulic safety parameters. The international CTF users’ group has currently more than 60 member-organizations from different countries including industry, regulation, national labs, consulting companies, research institutes and academia. The theory and physics models of CTF/CTFFuel will be presented first, followed by an interactive real-time demonstration on how to build fuel assembly and core models, execute the code in a serial and a parallel mode, and post process the results using different available tools.
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