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Comparison of In- and Ex-Situ Analysis of Post-Irradiation Annealing

Irradiation-assisted stress corrosion cracking (IASCC) refers to the intergranular of austenitic ironand nickel-base components in light water reactor (LWR) cores. IASCC is a complex phenomenon and both microstructural effects (radiation hardening) and microcompositional effects (radiationinduced segregation of major alloying elements; depletion of Cr, in particular) have been identified as potentially controlling mechanisms. While there is a reasonable understanding of radiationinduced segregation and radiation-induced microstructure, their exact roles in IASCC are unclear and identifying the controlling mechanism is a critical step in solving the problem. Post-irradiation annealing provides one means of isolating microcompositional changes from microstructural changes. Recent experimental [1,2] and simulation [3] studies have shown that dislocation loops are removed preferentially during post-irradiation annealing. Simulations also predict that dislocation loops can be removed completely while the microchemical changes remain unaffected. With this type of annealing process, the role of radiation-induced segregation (RIS) and/or microstructural changes in IASCC may be isolated.