Intergranular stress corrosion cracking initiation model of austenite stainless steels used in BWRs for optimized water chemistry control

Abstract

A calculation model on intergranular stress corrosion cracking (IGSCC) initiation time of materials used in boiling water reactors (BWRs) has been developed to evaluate effectiveness of water chemistry control for mitigation of the IGSCC. The model was composed of four terms which determine passive film break time:(1) a chemical term based on electrochemical corrosion potential (ECP) and impurity concentration; (2) a mechanical term based on strain rate; (3) a material term based on sensitization; and (4) an irradiation term based on acceleration of corrosion by γ -rays and neutron irradiation. The contribution of the chemical term in the passive film break was calculated based on a deterministic local corrosion model. Then, the local corrosion model was modified by adding mechanical acceleration of the film rupture to treat the IGSCC phenomenon. The model could reproduce the behavioral tendency seen in the slow strain rate tensile test on high carbon contents with sensitization heat treatment (for example, 620• C × 24 h). Under BWR operating conditions, IGSCC initiation time could be extended by a factor of 5 by lowering the electric conductivity from 1.0 to 0.06 μS/cm. If the ECP was reduced below the critical potential by a mitigation method, the IGSCC initiation time was predicted to become sufficiently long for pipings and components.

Effects of seawater components on radiolysis of water at elevated temperature and subsequent integrity of fuel materials

“…It was reported that gamma-ray irradiation promoted corrosion of SS [22,23]. Then, the anodic current of the 316L SS oxidation may increase enough to lower the ECP of 316L SS while overcoming the increase of DO and DHP by radiolysis of seawatermixed water.…”