Stable and Unstable Crack Growth of A508 Class 3 Plates Subjected to Combined Force of Thermal Shock and Tension

[+] Author and Article Information
G. Yagawa, Y. Ando

Department of Nuclear Engineering, University of Tokyo, Hongo, Bunkyo, Tokyo, Japan

K. Ishihara

Iron and Steel Research Laboratories, Sumitom Metal Industries, Amagasaki, Japan

T. Iwadate, Y. Tanaka

The Japan Steel Works, Ltd., Chatsu-machi, Muroran, Hokkaido, Japan

J. Pressure Vessel Technol 111(3), 234-240 (Aug 01, 1989) (7 pages) doi:10.1115/1.3265669 History: Received November 29, 1984; Revised February 03, 1989; Online November 05, 2009


An urgent problem for nuclear power plants is to assess the structural integrity of the reactor pressure vessel under pressurized thermal shock. In order to estimate crack behavior under combined force of thermal shock and tension simulating pressurized thermal shock, two series of experiments are demonstrated: one to study the effect of material deterioration due to neutron irradiation on the fracture behavior, and the other to study the effect of system compliance on fracture behavior. The test results are discussed with the three-dimensional elastic-plastic fracture parameters, J and Ĵ integrals.

Copyright © 1989 by ASME
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