Abstract
A material performance database for nuclear applications, which was named the JAERI Material Performance Database (JMPD), has been developed since 1986 with a view to utilizing various kinds of characteristic data of nuclear materials efficiently. The data stored in the JMPD are mainly fatigue crack growth data on low alloy steels, creep data on superalloys, tensile data on aluminum alloys and stress corrosion cracking data (slow strain rate testing (SSRT), crack growth rate, etc.) on austenitic stainless steels. Irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels in high temperature water has been considered as a degradation phenomenon potential not only in the light water reactors (LWRs) but rather common in systems where the materials are exposed simultaneously to radiation and water environments. This paper describes the present status of the JMPD, which is available through the Internet partially. Furthermore, some trials of utilization of the system focused on the issues relating to IASCC are mentioned as follows: the effect of alloy composition, dissolved oxygen and neutron fluence on IASCC susceptibilities and SCC growth rate could be drawn.
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