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As executive vice president for industry strategy at the Institute of Nuclear Power Operations, Jeff Place leads INPO’s industry-facing work, engaging directly with chief nuclear officers.
P. Hurst, H. C. Cowen
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 449-459
Technical Paper | Materials | doi.org/10.13182/NT55-449
Articles are hosted by Taylor and Francis Online.
Stress corrosion studies in caustic environments have been carried out on the ferritic 2 1/4 Cr—Mo steel, with particular reference to its use in the evaporators of the U.K. prototype fast reactor. The quench-hard-ened steel has been found to be susceptible to stress corrosion cracking (SCC) throughout the temperature range of 50 to 300°C. In 30% caustic soda at 116°C, this susceptibility extends over the potential range −900 to +100 mV (Hg/HgO). On tempering, SCC occurs at −900 to −700 mV, but only at more positive potentials when preceded by an overheating treatment. Mechanisms by which cracking occurs under the different conditions studied are discussed. Cracking can occur in hard tube-to-tube-plate welds exposed to caustic environments as a consequence of fabrication stresses, but it has been shown that this can be avoided by shot-peening.