January 1, 2002
Conference Paper

Light-Water Reactor Microstructural Characterization from Post-Irradiation Annealing Behavior

Abstract

A measurement and modeling approach has been used to interpret the character and stability of fine-scale microstructure in neutron irradiated stainless steel near 300 degrees C. The primary form of vacancy-type damage is concluded to reside in the detectable Frank loop population of the microstructure. Annealing behavior of hardness as well as microstructure indicate that more than one microstructural component contributes to measured irradiation-induced hardness. This includes a component very susceptible to short-term annealing, a component with expected dissolution behavior of Frank loops and a component that is very resistant to long-term annealing. The hardness recovery exhibits distinct differences in heat to heat variability that depends on irradiation dose. The character and stability of fine-scale microstructure is being investigated to better understand irradiation strengthening mechanisms, microstructures induced by neutron compared to proton irradiation, and predictions of transitions in microstructure from Frank loop dominance to void swelling dominance at temperatures greater than 300 degrees C.

Revised: November 2, 2006 | Published: January 1, 2002

Citation

Simonen E.P., D.J. Edwards, S.M. Bruemmer, J.T. Busby, and G.S. Was. 2002. Light-Water Reactor Microstructural Characterization from Post-Irradiation Annealing Behavior. In Tenth International Conference on Environmental Degradation Materials in Nuclear Power Systems - Water Reactors, August 5 to 9, Lake Tahoe, Nevada, USA, 12 pages. Houston, Texas:National Association of Corrosion Engineers. PNNL-SA-34962.