Май 10th, 2013
Pressure Vessel Technology. — 1999. — V. 121. -P. 4 9 -6 0 .17. Congleton J., H urst P. Slow strain ratestress conosion testing of RPV steels in high temperaturewater // Proc. 5-th Intern, symp. on environ.degradation of materials in nuclear powersystems-water reactors, California, USA, August2 5 -2 9 , 1991.- P . 4 3 9 -4 6 0 .18. Congleton J., Shoji Т., Parkins R. Thestress coiTOsion cracking of reactor pressure vesselsteel in high temperature water // CorrosionScience. — 1985. — Vol. 25, № 8/9. — P. 633 — 650.19. Cullen W.H. Fatigue Crack GrowthRates in Pressure Vessel and Piping Steels inLWR Environments // USNRC Report NUREG/CR-4724, March 1987. — 54 P.20. Davidson, J. Lankford. Fatique crackgrowth in metals and alloys: mechanisms andmicromcchanics // International Materials Reviews.1992. V. 37. № 2. P. 45 — 76.21. Eason E.D., Nelson E.E., Heys G.B.Fatigue Crack Growth Rate of Medium and LowSulfur Fcrritic Steels in Pressurized Water ReactorPrimary Water Environments // Pressure VesselTechnology. 2003. V. 125. P. 385 — 392.22. Effects of temperature and dissolvedcontent on fatigue life of carbon and low-alloysteels in LWR water environment / G. Nakao andct. al. // Fatigue and crack growth: environmentaleffects, modeling studies and design consideration.-N e w York, 1995. — P.
