Evaluation of intergranular stress corrosion cracking problems of stainless steel piping in Taiwan BWR-6 nuclear power plant

Nuclear Engineering and Design

Volumn 191, Issue 2, 1999, Pages 245-254

  Ting, Kuen ^a  

^a INSTITUTE OF NUCLEAR ENERGY RESEARCH   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; BOILING WATER REACTORS; CRACK PROPAGATION; FRACTURE TESTING; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; STAINLESS STEEL; STEEL TESTING; STRESS CORROSION CRACKING; WELDED STEEL STRUCTURES; WELDING CODES;

INTERGRANULAR STRESS CORROSION CRACKING (IGSCC);

STEEL PIPE;

EID: 0033155577     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00146-6     Document Type: Article

References (7)

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Rules for Inservice Inspection of Nuclear Power Plant Components, Boiler and Pressure Vessel Code Section XI. 1989.
2. Buchalet C.B., Bamford W.H. Stress intensity factor solution for continuous surface flaws in reactor pressure vessels. Mechanics of Crack Growth. 1976;. ASTM STP 590.
3. DeSalvo G., Gorman ANSYS Engineering Analysis System User's Information Manual and Theoretical Manual. 1991;Swanson Analysis System Inc.
4. Smith E. Theoretical justification of the association of a critical net-section stress with fracture initiation at a crack tip. Int. J. Pressure Vessels Piping. 8:1980;303-311.
5. Weld Overlay Shrinkage Effect Assessment Report For Second Nuclear Power Station Unit 1993 Outage. 1993;Taiwan Power Company. ZTP046.0210, Generic Letter 88-01, Supplement 1.
6. Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping. 1988;United States Nuclear Regulatory Commission (USNRC). NUREG 0313, Rev. 2, 1988.
7. NRC Position on IGSCC in BWR Austenitic Steel Piping. 1992;United States Nuclear Regulatory Commission (USNRC). Generic Letter 88-01, with Supplement 1, 1992.