Application of the FRI crack growth model for neutron-irradiated stainless steels in high-temperature water of a boiling water reactor environment
Keywords: واکنش پذیری بالقوه ی الکتروشیمیایی; BWR; boiling water reactor; CGR; crack growth rate; CT; compact tension; EPR; electrochemical potentiokinetic reactivation; FRI; fracture and reliability research institute at Tohoku University; GB; grain boundary; IASCC; irradiation assisted stress corro