Leak behavior of SCC degraded steam generator tubings of nuclear power plant

Nuclear Engineering and Design

Volumn 235, Issue 23, 2005, Pages 2477-2484

  Hwang, Seong Sik ^a   Kim, Hong Pyo ^a   Kim, Joung Soo ^a   Kasza, Kenneth E ^b   Park, Jangyul ^b   Shack, William J ^b  

^a Korea Atomic Energy Research Institute   (South Korea)

^b ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

HIGH TEMPERATURE EFFECTS; LEAKAGE (FLUID); PRESSURE EFFECTS; STEAM GENERATORS; STRESS CORROSION CRACKING; TUBES (COMPONENTS);

DESTRUCTIVE ANALYSIS; LEAK BEHAVIOR; STEAM GENERATOR TUBINGS;

NUCLEAR POWER PLANTS;

EID: 27644511666     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.06.013     Document Type: Article

References (5)

1. Diercks, D.R., Bakhtiari S., et al., 1998. Steam generator tube integrity program-annual report, NUREG/CR-6511, vol. 2, Argonne National Laboratory.
2. Diercks, D.R., Bakhtiari, S., et al., 2000. Steam generator tube integrity program-annual report, NUREG/CR-6511, AN vol. 7, ANL-0014, Argonne National Laboratory.
3. Kim, J.S., Hwang, S.S., et al., 1999. KAERI Internal Report (Korean). Destructive Analysis on Pulled Tubes from Ulchin Unit 1. Korea Atomic Energy Research Institute.
4. Majumdar, S., Kasza, Ken, et al., 2000. Pressure and leak rate tests and Models for failure of flawed steam generator tubes, NUREG/CR-6664, Argonne National Laboratory.
5. A. Zahoor Ductile Fracture Handbook 1989 Electric Power Research Institute Palo Alto, CA