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Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel Pages: 9 Published: Jan 1994
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View License Agreement Source: STP1175-EB Abstract The embrittlement of microalloyed and grain-refined high tensile strength steel plates, which are to be extensively used as structural components in nuclear reactors in India, was studied after irradiating to neutron fluences between 1.7 x 1017 and 1.0 x 1019 n.cm2 (E > 1 MeV). The irradiations were carried out at less than 150°C. The results of room temperature tension tests and the instrumented impact tests over a range of temperature are presented. Irradiation stability of the steel is monitored by measuring the increase in yield strength and the elevation in the ductile-brittle-transition temperature after neutron irradiation. Attempts have been made to assess the extent of embrittlement as a function of neutron exposure. The results have been compared with both vintage and advanced pressure vessel steels. Keywords: microalloyed ferritic steel, irradiation embrittlement, ductile-brittle-transition temperature (DBTT), static and dynamic yield strength, ductility, Charpy V-notch, neutron flux, neutron fluence, upper shelf energy Paper ID: STP23936S Committee/Subcommittee: E10.08 DOI: 10.1520/STP23936S ASTM International is a member of CrossRef. | ||