The crack growth rates(CGRs)of a domestic forged nuclear grade 316L SS piping material were measured at various temperatures and loading modes in simulated pressurized water reactor primary water environment using compact tension specimens.In this work,the simulated recirculating PWR primary water environment contained 1500 ppm B as H3BO3 and 2.3 ppm Li as LiOH.The ppm or ppb refers to weight percentages in this paper.A direct current potential drop(DCPD)technique was used to monitor CGRs throughout the tests.The fracture surface exhibited typical intergranular stress corrosion cracking(IGSCC)characteristics.CGRs increased monotonically with increasing temperature.CGRs under trapezoidal waveform loading were moderately higher than those under constant K loading.