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Additional resources for Elevated-Temp Ferritic, Martensitic Steels - Applications to Future Nuclear Reactors
Symposium on Structural Material for Service at Elevated Temperatures in Nuclear Power Generation, ed. A. O. Schaefer, Am. Soc. Mech. , New York, 375-385, 1975. 6. R. L. Klueh and D. R. , 2001. 7. S. N. , J. Nucl. , 85-86, 177-182 (1979). 8. R. L. Klueh, K. Ehrlich, and F. Abe, J. Nucl. , 191-194, 116-124 (1992). 9. R. W. , Panel Report on Low Activation Materials for Fusion Applications, UCLA Report PPG-778, University of California at Los Angeles, 1983. 10. G. J. Butterworth and O. N. Jarvis, J.
Banks, M. Blackler, J. Leggett, G. M. McColvin, S. Simpson, M. Smith, F. Starr, and R. W. Vanstone, The Institute of Materials, Minerals and Mining, London, 365-377, 2003. 79. F. Abe, T. Horiuchi, and M. Taneike, Parsons 2003: Engineering Issues in Turbine Machinery, Power Plant and Renewables, eds. A. Strang, R. D. Conroy, W. M. Banks, M. Blackler, J. Leggett, G. M. McColvin, S. Simpson, M. Smith, F. Starr, and 50 R. W. Vanstone, The Institute of Materials, Minerals and Mining, London, 379-395, 2003.
The stress exponent was approximately unity for the low-stress tests up to ≈100MPa. Above this stress, the exponent increased to 10 and higher. The authors pointed out that other work106 indicated that the two different creep-testing techniques did not always produce similar results. Although the two testing Fig. 17. Dependence of steady-state creep on stress for modified 9Cr-1Mo steel at 600-625ºC. 105 Based on Fig. 107 These tubes showed essentially no indication of creep deformation. Deformation would be expected if diffusion creep at 600ºC occurred in accordance with Fig.
Elevated-Temp Ferritic, Martensitic Steels - Applications to Future Nuclear Reactors