In-Pile Loop Experiment and Model Calculations for Radiolysis of PWR Primary Coolant

摘要

Optimization of the level of dissolved hydrogen (DH) in PWR primary coolant is believed to have several potential advantages. To assess the threshold value for reducing conditions, an in-pile loop experiment was performed. The in-pile response was monitored by measuring the corrosion potential of stainless steel against a Pt electrode. The results of the experiment were evaluated against computer modeling of radiolysis in the loop. General agreement was found between experimental data and modeling results. Both experiment and modeling indicate that the threshold DH value for radiolysis is much less than the present control level in PWR, while the in-core region is more easily affected by reduced DH level than the out-of-core region.