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Going Nuclear: Notes from the officially unofficial book tour
I work in the analytical labs at one of Europe’s oldest and largest nuclear sites: Sellafield, in northwestern England. I spend my days at the fume hood front, pipette in one hand and radiation probe in the other (and dosimeter pinned to my chest, of course). Outside the lab, I have a second job: I moonlight as a writer and public speaker. My new popular science book—Going Nuclear: How the Atom Will Save the World—came out last summer, and it feels like my life has been running at full power ever since.
Youho Lee, Thomas J. McKrell, Chao Yue, Mujid S. Kazimi
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 210-227
Technical Paper | Fuel Cycle and Management/Materials for Nuclear Systems | doi.org/10.13182/NT12-122
Articles are hosted by Taylor and Francis Online.
An experimental assessment was conducted of the silicon carbide (SiC) cladding oxidation rate in steam under conditions that are representative of loss-of-coolant accidents in light water reactors (LWRs). SiC oxidation tests were performed with monolithic alpha-phase tubular samples at atmospheric pressure for steam temperatures of 1140°C and 1500°C and a Reynolds number range of 40 to 330. Linear weight loss of SiC samples due to boundary layer controlled reaction of silica scale (SiO2 volatilization) was experimentally observed. The weight loss rate increased with increasing steam flow rate and temperature. Over the range of test conditions, SiC oxidation rates were shown to be about three orders of magnitude lower than the oxidation rates of Zircaloy-4. This underlines a weaker interplay between oxidation and mechanical property degradation in comparison with Zircaloy. SiC volatilization correlations for developing laminar flow in a vertical channel were formulated for LWR accident modeling.