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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.”
M. R. Louthan, Jr., J. A. Donovan, G. R. Caskey, Jr.
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 192-200
Technical Paper | Material | doi.org/10.13182/NT75-A24418
Articles are hosted by Taylor and Francis Online.
Tritium absorption was determined in Type 304L austenitic stainless steel by analyzing concentration gradients obtained during prolonged exposures to high-pressure gaseous tritium. The calculated tritium diffusivities at temperatures greater than 373 K were shown to be in excellent agreement with the equation where m is the isotopic mass. This equation was previously developed for deuterium in several types of austenitic stainless steels. There was strong evidence for “short-circuit” diffusion paths and a grain size effect on tritium absorption. Such effects are assumed to cause the tritium diffusivities measured for exposures at less than 373 K to be higher than expected from the above equation. Cold work, either prior to or during exposure, significantly increased the effective tritium diffusivity. The increase in tritium diffusivity observed in the samples cold-worked prior to exposure is believed to be caused by preferential (short-circuit) diffusion through strain-induced martensite. The increase in diffusivity in specimens deformed during exposure is believed to be caused by enhanced tritium transport with moving dislocations. This analysis of concentration gradients also shows that tritium permeation rates through austenitic stainless steels will often be significantly less than rates expected from analysis of diffusion-controlled transport properties. This is because of surface barriers that limit tritium absorption, even at pressures to 69 MPa. Solubilities derived from analyses of the concentration gradients were consistently lower than expected and were significantly influenced by specimen surface conditions.