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This article describes probabilistic calculations that address intergranular stress corrosion cracking of stainless steel piping; a degradation mechanism of major concern to nuclear pressure boundary integrity. The objective is to simulate the cracking of stainless steel piping under intergranular stress corrosion cracking conditions, and to evaluate the structural reliability using remedial actions for intergranular stress corrosion cracking that are limited to benefits of in-service inspections and the induction heating stress improvement process. The results show that an effective in-service inspection requires a suitable combination of flaw detection capability and inspection schedule, and it has been suggested that the residual stresses could be altered to become favorable, thereby improving the reliability piping.

In this paper, the work is based on the application of probabilistic fracture mechanics models (PFM) to predict the reliability of nuclear reactors pipes under pressure. Cracking simulation of a stainless steel piping under the conditions of intergranular stress corrosion cracking (IG-SCC) is based on the general methodology recommended in the modified software M-PRAISE. IG-SCC is characterized by a unique damage parameter depending on residual stresses, environmental conditions, and sensitization degree. This parameter can be used to evaluate the structural reliability and identify the majority of efficient approaches to improve the piping reliability: effect of a corrosive medium on the reliability, which is analyzed in this present work.

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