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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.
Qi Xu, T. Nagasaka, T. Muroga
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 609-612
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1555
Articles are hosted by Taylor and Francis Online.
Fe-Cr-W based low activation ferritic steels are widely regarded as promising blanket structural materials for fusion reactors, while liquid lithium breeder/coolant concept provides an attractive option for high efficiency and simplicity of blanket system. However, past compatibility tests of ferritic steels with liquid lithium were almost limited to conventional Fe-Cr-Mo steels. In this study, the corrosion behavior of the candidate reduced activation ferritic steel, JLF-1(Fe-9Cr-2W-0.1C) in lithium was investigated. Static immersion tests were carried out using coupon specimens (16 × 4 × 0.25 mm) at 873K and 973K for 100hr. At 973K, the phase transformation from martensite to ferrite resulted in decrease in hardness from 250 to 140Hv. This seemed to be caused by depletion of C. Examinations of binary Fe-Cr and pure iron were also carried out for comparison with JLF-1.