PWR full-reactor coolant system decontamination

The overall objective of the current program is to identify and address all aspects of full system decontamination with the purpose of qualifying at least one process for PWR use. The objective of the current study is to provide baseline data on the performance of materials on the primary side after exposure to three cycles of the LOMI process. The technical feasibility of applying this process will be determined in a subsequent task. The general corrosion characteristics of over 39 materials were evaluated for some combinations of material, type of specimen (coupon and creviced coupons), and loop velocity (0, 5, 20 and about 150 ft/sec). At velocities of less than or equal to 20 ft/sec, sixteen types of specimens were employed to evaluate localized corrosion and stress corrosion cracking. Some of the specimens were examined after one cycle and all of the specimens after three cycles of exposure. Hybrid expansion joints were also evaluated after an additional, simulated steam generator exposure to beginning-of-life reactor coolant for 90 days. The results of these evaluations are presented in this report. 10 figs., 8 tabs