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Fusion Science and Technology
Latest News
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.”
H. J. Ahn, J. Park, K. Song, B-C Na, S. Rosanvallon, D. Stout
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1006-1009
Measurement, Monitoring, and Accountancy | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12586
Articles are hosted by Taylor and Francis Online.
ITER is trying to develop destructive and non-destructive methods of tritium measurement for discarded radwaste components. The ITER Type B(medium activity with long life) metallic radwastes that need tritium measurement are mainly Divertor Cassette Body, Blanket Modules, Test Blanket Module Port Plug, Torus Cryopump, etc. It has been known that 107 Bq/g of tritium is distributed within 1 mm depth from the surface of the metallic radwastes. The metallic radwastes generated from maintenance period of ITER facility will be transferred to the Hot Cell Facility (HCF) for treatment including cutting, tritium removal and pre-packaging, followed by being shipped to the disposal facility after interim storage at ITER site.In this study, the radiochemical analysis methods of tritium measurement for ITER type B metallic radwastes were reviewed. Especially, two experimental methods, chemical acid leaching method (CALM) and heating method (HM,) were compared with each others to suggest the most suitable method for tritium measurement. The recovery yield of tritium standards for CALM and HM showed excellent results of 98 and 90 %, respectively. Since HM requires post treatment of extracted tritium species due to impurities, as shown in the analysis of sample from Nuclear Power Plant, CALM was considered more efficient method than HM for tritium analysis of Type B metallic radwastes.
