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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.”
P. K. Mioduszewski, L. W. Owen, D. A. Spong, M. E. Fenstermacher, A. E. Koniges, T. D. Rognlien, M. V. Umansky, A. Grossman, H. W. Kugel
Fusion Science and Technology | Volume 51 | Number 2 | February 2007 | Pages 238-260
Technical Paper | doi.org/10.13182/FST07-A1302
Articles are hosted by Taylor and Francis Online.
Plasma boundary control in stellarators has been shown to be very effective in improving plasma performance and, accordingly, is an important element from the very beginning of the National Compact Stellarator Experiment (NCSX) design. Studies of the magnetic field topology outside the last closed magnetic surface (LCMS) indicate the possibility of many toroidal revolutions of field lines launched within a couple of centimeters of the LCMS. Field line connection lengths, typically in the order of 100 m, should be sufficient to allow for the necessary separation of divertor and separatrix temperatures. In the top and bottom of the bean-shaped cross section (toroidal angle = 0), a field expansion of >5 is observed, which will help to spread out the heat flux on limiters and divertor plates. Plasma-facing components (PFCs) will be developed systematically according to our respective understanding of the NCSX boundary; the phased PFC development will start out with a set of limiters and has the eventual goal to develop a divertor with all the benefits of impurity and neutrals control. Neutrals calculations have been started to investigate the effect of neutrals penetration at various plasma cross sections, especially at the location of = 0 deg. Advanced wall conditioning techniques, as employed in other major fusion devices, will be incorporated in the NCSX operation.