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Comparison of Radiation Damage Studies and Fuel Cladding Performance for Lncoloy-800
H. J. Busboom
F. A. Comprelli
C. N. Spalaris
出版
ASTM International
, 1969
URL
http://books.google.com.hk/books?id=qUJ7zgEACAAJ&hl=&source=gbs_api
註釋
Postirradiation tension and burst tests were performed at 593 and 704 C on materials from various heats of Incoloy-800 to establish the effect of irradiation on short-term mechanical properties for fast fluences to 6.25 x 1021 n/cm 2. Two types of tension specimens were tested: precut sheet specimens that were prepared prior to irradiation, and fuel clad specimens prepared from irradiated Mark II EVESR fuel rods. At the highest fiuences, uniform elongations of 1.5 to 2.0 percent have been measured for precut specimens. The uniform elongation was found to be dependent upon the strain rate at which the specimen was tested. Comparable fuel cladding properties at this fluence are not yet available. At a fast fluence of 5.7 x 1020 n/cm 2, precut specimens exhibited uniform elongations of 11.5 to 16.8 percent whereas fuel clad exhibited 2.6 to 6.0 percent for similar fluence and test conditions. It was concluded that the greater degradation of ductility in fuel cladding specimens was associated with both nonuniform (and often higher) temperature and plastic strain experienced during the irradiation period.