Stress corrosion cracking of sensitized type 304 stainless steel in 288C water: A five laboratory round robin

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

Volumn , Issue , 1999, Pages 423-433

  Andresen, Peter L ^a   Gott, Karen ^b   Nelson, J Lawrence ^c  

^a GE GLOBAL RESEARCH   (United States)

^b Swedish Radiation Protection Authority   (Sweden)

^c ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; CRACK PROPAGATION; FATIGUE OF MATERIALS; FRACTURE MECHANICS; LIGHT WATER REACTORS; MECHANICAL TESTING; MECHANICAL VARIABLES MEASUREMENT; STRESS CORROSION CRACKING;

BOUNDING DISPOSITION RESPONSE; CORROSION POTENTIAL;

STAINLESS STEEL;

EID: 0033489076     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch43     Document Type: Conference Paper

References (9)

1. P. M. Scott, "Recommended Test Procedure for Studies on Crack Growth in Simulated LWR Water Environments", Proc. Third Intl. Atomic Energy Agency Specialists Mtg on Subcritical Crack Growth, Moscow, USSR, May 1990, NRC NUREG/CP-0112 (ANL-90/22), Vol. 1, p. 117-128.
2. P. L. Andresen, "IGSCC Crack Propagation Rate Measurement in BWR Environments: Executive Summary of a Round Robin Study", SKI Report 98:27, ISSN 1104-1374, ISRN SKI-R-98/27-SE, SKI, Stockholm, 1999.
3. "IGSCC Crack Propagation Rate Measurement in BWR Environments", Detailed reports from all laboratories, SKI Report 98:27, ISSN 1104-1374, ISRN SKI-R-98/27-SE, SKI, Stockholm, 1999.
4. "Statens kärnkraftinspektions föreskrifter om mekaniska anordningar i kärntekniska anläggningar", SKIFS 1994:1, ISSN 1400-1187, SKI, Stockhom, Sept. 26, 1994.
5. W. S. Hazelton and W. H. Koo, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping", NUREG 0313 Rev. 2, US NRC, Jan. 1988.
6. F. P. Ford, D. F. Taylor, P. L. Andresen and R. G. Ballinger, "Corrosion Assisted Cracking of Stainless Steel and Low Alloy Steels in LWR Environments", Report NP5064S, EPRI, Palo Alto, Feb. 1987.
7. F. P. Ford and P. L. Andresen, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors", in "Corrosion Mechanisms", Ed. P. Marcus and J. Ouder, Marcel Dekker, p. 501-546, 1994.
8. P. L. Andresen and F. P. Ford, "Life Prediction by Mechanistic Modelling and System Monitoring of Environmental Cracking of Fe & Ni Alloys in Aqueous Systems", Mat'ls Sci. and Eng., A103, p. 167-183, 1988.
9. P. L. Andresen, "SCC Testing and Data Quality Considerations", Ninth Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, 1999.