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Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor

VK. ShamardinVS. NeustroevAV. PovstyankoTM. BulanovaZE. OstrovskyAA. KuznetzovIP. KursevitchVA. Nikolaev

出版	ASTM International, 1996
URL	http://books.google.com.hk/books?id=ygt-zgEACAAJ&hl=&source=gbs_api

註釋Specimens from fuel assembly wrappers and control rod cases of 0.07C-15Cr-35Ni-3Mo-B-Zr-Y alloy were investigated after irradiation in the BOR-60 and BN-600 reactors up to a maximum damage dose of about 110 dpa at temperatures between 340 to 550°C.