Creep-fatigue interaction of inconel 617 at 950°C in simulated nuclear reactor helium

Materials Science and Engineering

Volumn 104, Issue C, 1988, Pages 37-51

  Bhanu Sankara Rao, K ^a   Meurer, H P ^b   Schuster, H ^a  

^a FORSCHUNGSZENTRUM JÜLICH   (Germany)

^b Internationale Atomreaktorbau GmbH   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

FRACTURE MECHANICS; METALS TESTING--FATIGUE; NUCLEAR REACTORS, GAS COOLED--MATERIALS; STRAIN--ANALYSIS;

CARBIDE PRECIPITATES; CREEP-FATIGUE INTERACTION; INCONEL ALLOY 617; INTERGRANULAR CREEK CRACKS; LOW CYCLE FATIGUE; SURFACE FATIGUE CRACKS;

NICKEL AND ALLOYS;

EID: 45449122369     PISSN: 00255416     EISSN: None     Source Type: Journal    
DOI: 10.1016/0025-5416(88)90404-1     Document Type: Article

References (24)

1. Status of metallic materials development for application in advanced high-temperature gas-cooled reactors
2. Proc. Specialists' Meet. on High Temperature Metallic Materials for Application in Gas Cooled Reactors
3. Proc. Specialists' Meet. on High Temperature Metallic Materials for Application in Gas Cooled Reactors
4. On the failure condition in strain-controlled low cycle fatigue
5. Influence of time and temperature dependent processes on strain controlled low cycle fatigue behavior of alloy 617
6. Fatigue, tensile and relaxation behaviour of stainless steels