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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.”
Mahmoud Z. Youssef, Hesham Khater, Mike Kotschenreuther
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 804-809
Chamber Technology | doi.org/10.13182/FST01-A11963338
Articles are hosted by Taylor and Francis Online.
Plasma stabilization and plasma elongation are best achieved by keeping a stabilizing shell as close as possible to the plasma. In CLiFF design, a 2-cm-thick flowing liquid layer is placed in front of a solid FW and is thought to be used as an active conduction shell if its conductance is relatively high such as with liquid lithium. On the other hand, higher conductance is achieved by solid shells (e.g. Cu, Al, FS, W, V alloy). In the present study, the adverse effect of this stabilizing shell (whether it is liquid or solid material) on tritium breeding ratio (TBR) is investigated. Among the design features that quantify this effect are: the type of breeder and structure, the degree of Li-6 enrichment, the material and thickness of the shell, and whether or not there is a front beryllium multiplying zone in the blanket. Additionally, the presence of a solid conducting shell near the FW will impose a safety concern in the case of LOCA. The present study addresses this concern and comparison of the level of decay heat and waste disposal rating is made among the candidate materials for the stabilizing shell.