Qualification and application of instrumented specimens for in-core studies on cracking behaviour of austenitic stainless steels

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Volumn , Issue , 1999, Pages 951-961

  Karlsen, T M ^a   Hauso, E ^a  

^a OECD HALDEN REACTOR PROJECT   (Norway)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITE; BOILING WATER REACTORS; CRACK INITIATION; CRACK PROPAGATION; LIGHT WATER REACTORS; NEUTRON IRRADIATION; STRESS CORROSION CRACKING; TENSILE PROPERTIES;

AUSTENITIC STAINLESS STEEL; HYDROGEN WATER CHEMISTRY; IRRADIATION ASSISTED STRES CORROSION CRACKING;

STAINLESS STEEL;

EID: 0033489186     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch100     Document Type: Conference Paper

References (9)

1. D. Weinstein, "Real Time, In-reactor Monitoring of Double Cantilever Beam Crack Growth Sensors", Proc. Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. R.E. Gold, E.P. Simonen (1993), 645-649.
2. C. Vitanza and T. Karlsen "In-pile IASCC Test Programme in the Halden Reactor", Proc. Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. R.E. Gold, E.P. Simonen (1993), 651-656
3. S. Dumbill, "Microanalysis of Irradiated Steels from Halden IASCC Rigs IFA 586 and IFA 605", Halden Work Report (HWR-474), April 1994
4. P.L. Andresen (GE CR&D, Schenectady, USA) and K. Petterson (Materials Science and Engineering, KTH, Stockholm, Sweden) private communications
5. ASTM E-399-90 "Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials"
6. G.R. Odette and G.E. Lucas "The Effects of Intermediate Temperature Irradiation on the Mechanical Behaviour of 300-Series Austenitic Stainless Steels", Journal of Nuclear Materials 179-181 (1991), 572-576.
7. M. Valo, "Fracture Toughness and Tensile Properties of Irradiated Austenitic Stainless Steel Components Removed from Service" DNo REA 35/91 September 1993, VTT Reactor Laboratory
8. P.L. Andresen (GE CR&D, Schenectady, USA) private communication
9. M. Mayuzumi, et al. "Development of an In-core Stress Corrosion Cracking Test Method and Preliminary Test Results", Corrosion 55 (1999), 166-172.