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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.”
C. E. Sessions, S. D. Reynolds, Jr., M. A. Hebbar, J. F. Lewis, J. H. Kiefer
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 270-279
Technical Paper | Materials | doi.org/10.13182/NT55-270
Articles are hosted by Taylor and Francis Online.
The progress achieved since 1977 in the important area of materials and processes development of fast reactor steam generator development is summarized. The two distinguishing features of the proposed Westinghouse-Tampa steam generator concept are the convoluted shell expansion joint (CSEJ) and the double-wall tubing with a third fluid leak detection capability. A Cr—1 Mo low alloy steel will be used for all important parts of the generator including the CSEJ and the tubes. Other areas in which progress was made include tube-to-tubesheet (TITS) welding, post-weld heat treatment (PWHT), tube expansion, and development of materials specifications for prototype and future plant materials. The tubing development work was based on the successful completion of a manufacturing feasibility program in 1974. This activity has involved manufacture of 23.47-m (77-ft)-long pre-stressed double-wall tubing (DWT) and testing of the tubing for dimensional tolerance or control interface residual stress, heat transfer, interface wear, and gas flow rates at the DWT interface. Results illustrate the capabilities of the vendors’ tube manufacturing process in achieving the important attributes of a leak detecting, prestressed, double-wall steam generator concept. The CSEJ material selection and design have evolved significantly since 1977. A materials change from Alloy 600 to Cr—1 Mo was recently made. The approach to manufacturing the CSEJ is to machine the convolutes from a large pre-forged ring of remelt Cr—1 Mo steel. Significant welding and PWHT process development progress has been achieved for both accessible and inaccessible T/TS welds. Equipment has been designed and manufactured successfully, and welding parameter development is well under way. Automatic and manual welding guns utilizing the pulsed current technique are described. The approach to PWHT involves induction heating for short times at a relatively high tempering temperature. Temperature control of the induction unit involves a preprogrammed heating cycle and feedback control using infrared sensors or thermocouples.
