CRACK GROWTH RESPONSE OF ALLOY 690 IN SIMULATED PWR PRIMARY WATER

December 1, 2009

Conference Paper

CRACK GROWTH RESPONSE OF ALLOY 690 IN SIMULATED PWR PRIMARY WATER

Abstract

The stress corrosion crack growth response of three extruded alloy 690 CRDM tube heats was investigated in several thermomechanical conditions. Extremely low propagation rates (

Revised: February 10, 2012 | Published: December 1, 2009

Citation

Toloczko M.B., and S.M. Bruemmer. 2009. CRACK GROWTH RESPONSE OF ALLOY 690 IN SIMULATED PWR PRIMARY WATER. In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, August 23-27, 2009, Virginia Beach, Virginia, 706-721. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-72539.