Abstract
Yield strength, tensile strength and uniform elongation of unirradiated and irradiated reactor pressure vessel steels were determined by the modified miniature specimen test (MMST). The facility and conditions for irradiating the miniature specimens are described. The results were compared with conventional tensile test data. Empirical formulas for correcting result errors caused by the deviation of specimen thickness were established. The application of the MMST technique to radiation surveillance for pressurized water reactor components is addressed.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callMore From: International Journal of Pressure Vessels and Piping
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
