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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.”
L. Green, M.D. Carelli, F. Stefani, G. Dave Morgan, V. Dennis Lee, R. Mattas
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 300-315
International Thermonuclear Experimental Reactor (ITER) | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40178
Articles are hosted by Taylor and Francis Online.
Changes in ITER requirements and conditions in the Engineering Design Activity (EDA), and the desire to obtain greater operating flexibility, led to a reconsideration of the ITER Conceptual Design Activity (CDA) blanket designs. The current strategy is to follow a two-tiered development approach: The reference design blanket is non-breeding, and satisfies only the basic performance phase (BPP) functional requirements. This blanket would need to be changed out for the extended performance phase (EPP). A lower level development effort is also underway on an tritium-breeding blanket. The decision as to which of the two designs to adopt will be made at the end of a two-year development effort. This paper describes the present candidate blankets and the issues associated with each of them. The reference design is a non-breeding, low temperature, low pressure, water cooled, austenitic stainless steel (316SS) blanket/shield (BS). The first wall (FW), which may be integral with or separate from the BS, is a bonded copper-alloy/SS structure with a beryllium coating. Critical issues here are copper-SS bonding, fabricability, and radiation damage and stress corrosion cracking of the SS. The breeding blanket utilizes vanadium alloy structural material, with lithium as the breeder. The coolants are either lithium (self-cooled) or high pressure helium. The primary issues here are the need to electrically insulate the flow channels, the qualification of vanadium as a structural material, and the fabrication of large vanadium structures.
