Status of JAERI material performance database (JMPD) and analysis of irradiation assisted stress corrosion cracking (IASCC) data
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
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 aluminium 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 light water reactors (LWRs) but in the rather common systems where the materials are exposed to radiation in the presence of water.This paper describes the present status of the JMPD, which is partially available through the internet. Furthermore, some trials for the utilization of the system focused on the issues relating to IASCC are mentioned. The effect of alloy composition, dissolved oxygen and neutron fluence on IASCC susceptibilities and SCC growth rate could be drawn. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 37
- Journal Issue
- 11
- Journal Page Range
- p. 949-958
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32007520
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ALUMINIUM ALLOYS; AUSTENITIC STEELS; CRACK PROPAGATION; CREEP; DOCUMENTATION; FATIGUE; HIGH ALLOY STEELS; JAERI; LOW ALLOY STEELS; NEUTRON FLUENCE; OXYGEN; RADIATION EFFECTS; REACTOR MATERIALS; STRESS CORROSION; TENSILE PROPERTIES; WATER CHEMISTRY; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CORROSION; ELEMENTS; IRON ALLOYS; IRON BASE ALLOYS; JAPANESE ORGANIZATIONS; MATERIALS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NONMETALS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 24 refs; 15 figs., 1 tab.