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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.”
S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 601-609
Technical Paper | Fusion Energy - Inertial Fusion Technology | doi.org/10.13182/FST05-A752
Articles are hosted by Taylor and Francis Online.
This paper provides an overview of experimental and numerical studies conducted at Georgia Tech to assess the fluid dynamics aspects of liquid protection schemes for fusion energy reactors. The problems described here include: (1) Dynamics of slab jets for thick liquid protection, including the effect of nozzle design, flow conditioning, and boundary layer cutting on jet surface smoothness; (2) Primary turbulent breakup of turbulent liquid sheets and forced thin liquid films, and quantification of the associated hydrodynamic source term; (3) Dynamics of forced films on downward-facing flat and curved surfaces, including film detachment and flow around beam ports; (4) Free-surface topology and drop detachment from downward-facing porous wetted walls; and (5) Thermocapillary effects and associated design constraints for liquid-film-protected divertors and first walls.The experimental data and validated numerical models developed in these studies allow reactor designers to identify design windows for successful operation of liquid-protected first walls and plasma facing components in inertial and magnetic confinement systems.
