Fracture in ferritic reactor steel—dynamic strain aging and cyclic loading

Author:

Murty K. Linga,Seok Chang-Sung

Publisher

Springer Science and Business Media LLC

Subject

General Engineering,General Materials Science

Reference23 articles.

1. L.E. Steele, “Review and Analysis of Reactor Vessel Surveillance Programs,” Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects, ASTM STP 784 (Philadelphia, PA: ASTM, 1983), p. 227.

2. G.E. Lucas et al., “Effects of Composition and Temperature on Irradiation Hardening of Pressure Vessel Steels,” Proc. of the Fifth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), pp. 696–703.

3. M.S. Wechsler and K.L. Murty, “Impurity-Defect Interactions and Radiation Hardening and Embrittlement in BCC Metals,” Met. Trans. A, 20A (1989), pp. 2637–2649.

4. Y.H. Jung and K.L. Murty, “Effect of Interstitial Impurities on Fracture Characteristics of A533B Class 1 Pressure Vessel Steel,” Influence of Radiation on Mechanical Properties: 13th Int. Symp., ASTM STP 956 (Philadelphia, PA: ASTM, 1987), pp. 395–407.

5. J.H. Hong and K.L. Murty, “Effect of Dynamic Strain Aging and Neutron Irradiation on Fracture Characteristics of Various Steels and Iron,” Proc. of ASM Symp. on Microstructure and Mechanical Properties of Aging Materials (Materials Park, OH: ASM, 1992), pp. 391–397.

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