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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.”
J.M. Miller, W.R.C. Graham, S.L. Celovsky, J.R.R. Tremblay, A.E. Everatt
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1077-1081
Isotope Separation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22749
Articles are hosted by Taylor and Francis Online.
A 5 Mg/annum Combined Electrolysis Catalytic Exchange (CECE) Facility was designed, constructed and operated to demonstrate the CECE process for heavy water detritiation. In this demonstration facility, a liquid-phase catalytic exchange (LPCE) column, using AECL's wetproofed catalyst, separated tritium from deuterium and a specially designed, low-inventory electrolytic cell provided tritium-enriched deuterium to the LPCE column. An overhead recombiner, also using wetproofed catalyst, produced detritiated heavy water. Tritium was removed from the electrolysis cell as tritiated deuterium gas and packaged as a titanium deuteride. The design detritiation factor of 100 was readily achieved using a 370 GBq/kg heavy water feed. Design features, operational experience and results from the 4-month, 2 000-h operation are described.
