Abstract
The ductile-brittle transition temperature (DBTT) of 9Cr-1Mo steel was characterized by an RT NDT-based K IR curve approach and a reference temperature (T 0)-based master curve (MC) approach. The MC was developed at a dynamic loading condition (loading rate of 5.12 m/s), using precracked Charpy V-notch (PCVN) specimens, and the reference temperature was termed T dy0 . The RT NDT and T dy0 were determined to be −25 °C and −52 °C, respectively. The T dy0 was also estimated from instrumented CVN tests, using a modified Schindler procedure to evaluate K Jd ; the result shows close agreement with that obtained from the PCVN tests. The ASME K IR -curve approach proves to be too conservative compared to the obtained trend of the fracture toughness with temperature. The cleavage fracture stress, σ* f , estimated from the critical length, l*, shows good agreement with that estimated from the load-temperature diagram (2400 to 2450 MPa), which was constructed from the CVN test results. The crack initiation mechanism has been identified as decohesion of the particle-matrix interface, rather than as the fracture of the particles.
Article PDF
Similar content being viewed by others
Avoid common mistakes on your manuscript.
References
C. Brown, V. Levy, J.L. Seran, K. Ehrlich, R.J.C. Roger, and H. Bergmann: Fast Reactors and Related Fuel Cycles-FR91, Atomic Energy Society, Tokyo, 1991, vol. 1.
C. Brown, R.J. Lilley, and G.C. Crittenden: Nucl. Eng., 1994, vol. 35, p. 122.
E. Materna-Morris and K. Ehrlich: Proc. Technical Committee Meeting on Influence of High Dose Irradiation on Advanced Reactor Core Structural and Fuel Materials, Obninsk, Russian Federation, 16–19 June 1997, IAEA-TECDOC-1039, August 1998, p. 129–138. ISSN. 1011-4289.
A.J. Lovell, A.I. Fox, W.H. Sutherland, and S.L. Hecht: Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, LaGrange Park, IL, 1987, pp. 3–25.
V.S. Khabarov, A.M. Dvoriashin, and S.I. Porollo: Proc. Technical Committee Meeting on Influence of High Dose Irradiation on Advanced Reactor Core Structural and Fuel Materials, IAEA-TECDOC-1039, Vienna, 1998, p. 139.
S. Nomura, S. Shikakura, S. Ukai, I. Seshimo, M. Harada, I. Shibabara, and M. Katsuragawa: Rast Reactors and Related Fuel Cycles-FR 91, Atomic Energy Society, Japan, Tokyo, 1991, vol. 1.
J.L. Seran, V. Levy, P. Dubuisson, D. Gilbon, A. Maillard, A. Fissolo, H. Touron, R. Cauvin, A. Chalony, and E. Le Boulbin: Proc. Int. Symp. on Effects of Radiation Materials, ASTM STP 1125, N.H. Packan, R.S. Stoller, A.S. Kumar, and D.S. Gelles, eds., ASTM, West Conshohocken, PA, 1992, p. 1209.
A. Kohyama, A. Hishinuma, D.S. Gelles, R.L. Klueh, W. Dietz, and K. Ehrlich: J. Nucl. Mater., 1996, vols. 231–237, p. 138.
J.L. Seran, A. Alamo, A. Maillard, H. Touron, J.C. Brachet, P. Dubuisson, and O. Rabouille: J. Nucl. Mater., 1994, vols. 212–215, p. 588.
N.L. Hu, and D.S. Gelles: Influence of Radiation on Material Properties, ASTM, STP 956, 1987, p. 83.
Preliminary Safety Analysis Report of PFBR, Reactor Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkan, India, 2002.
ASME Boiler and Pressure Vessel Code, Section III, Nuclear Power Plant Components, Div. 1, Appendix G, ASME, New York, NY, 1980.
ASME Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Div. 1, Appendix A, ASME, New York, NY, 1980.
J.D. Landes and D.H. Shaffer: Scientific Paper No. 79-ID3-JINTF-P4, Westinghouse, Pittsburgh, PA, 1979.
K. Wallin, T. Saario, and K. Torroren: Met. Sci., 1984, vol. 18, p. 13.
K. Wallin: Eng. Fract. Mech., 1984, vol. 19, p. 1085.
K. Wallin: Eng. Fract. Mech., 1985, vol. 22, p. 149.
K. Wallin: Proc. Joint IAEA/CSNI Specialist Meeting on Fracture Mechanics Verification by Large-Scale Testing, NUREG/CP-0131 (ORNL/TM-12413), Oct. 1993, 1992 ORNL, Oak Ridge, TN, p. 465.
K. Wallin: Advances in Fracture Research (Proc. Int. Conf. Fracture, ICF-9), B.L. Karihaloo, Y.W. Mai, M.I. Ripley, and R.O. Ritchie, eds. Sydney, Australia, 1997, vol. 5, p. 2333.
W. Server, S. Rosinski, R. Lott, C. Kim, and D. Weakland: Int. J. Press. Ves. Piping, 2002, vol. 79, p. 701.
B.Z. Margolin, V.A. Shvetsova, A.G. Gulenko, A.V. Ilyin, V.A. Nikolaev, and V.I. Smirnov: Int. J. Press. Ves. Piping, 2002, vol. 79, p. 219.
Test Method for Determination of Reference Temperature, T o , for Ferritic Steels in the Transition Range, ASTM E 1921–97, ASTM, West Conshohocken, PA, 1997.
1990 Annual Book of ASTM Standards, ASTM Standard E 208–87a, ASTM, West Conshohocken, PA, 1990, vol. 03.01, p. 260.
1990 Annual Book of ASTM Standards, ASTM Standard E 23–88, ASTM, West Conshohocken, PA, 1990, vol. 03.01, p. 197.
K.K. Yoon, J.B. Hall, Van Der Sluys, M. Higuchi, and K. Lida: 2001 ASME Pressure Vessel and Piping Conf., Atlanta, GA, July 23–26, 2001, p. 1.
H.J. Schindler, T. Varga, D.H. Njo, and G. Prantl: Materials Aging and Component Life Extension, Proc. Int. Symp. on Material Ageing and Component Life Extension, Milan, Italy, Oct. 10–13, 1995, V. Bicego, A. Nitta, and R. Viswanathan, eds., vol. 2, p. 1367.
P.R. Sreenivasan and S.L. Mannan: Int. J. Fract., 2000, vol. 101, p. 229.
H.J. Schindler: Pendulum Impact Testing: A Century of Progress, ASTM STP 1380, ASTM, West Conshohocken, PA, 2000, p. 337.
P.R. Sreenivasan, C.G. Shastry, M.D. Mathew, K.B.S. Rao, S.L. Mannan, and G. Bandyopadhyay: J. Eng. Mater. Technol. (Trans. ASME), 2003, vol. 125, p. 227.
S. Ortner: Int. J. Press. Ves. Piping, 2002, vol. 79, p. 693.
A. Moitra, P.R. Sreenivasan, S.K. Ray, and S.L. Mannan: Int. J. Press. Ves. Piping, 1996, vol. 69, p. 253.
A. Moitra: Ph.D. Thesis, Banaras Hindu University, Varanasi, India, 2003.
R.O. Ritchie, J.F. Knott, and J.R. Rice: J. Mech. Phys. Solids., 1973, vol. 21, p. 395.
G.R. Odette and G.E. Lucas: J. Nucl. Mat., 1983, vol. 117, p. 264.
R.M. McMeeking: J. Mech. Phys. Solids, 1977, vol. 25, p. 357.
S.K. Ray, P.R. Sreenivasan, K.G. Samuel, and P. Rodriguez: Int. J. Press. Ves. Piping, 1993, vol. 54, p. 481.
R.A. Wullaert: Impact Testing of Metals, ASTM STP 466, ASTM, West Conshohocken, PA, 1970, p. 148.
D.A. Curry and J.F. Knott: Met. Sci., 1976, vol. 10, p. 1.
D.A. Curry and J.F. Knott: Met. Sci., 1978, vol. 12, p. 511.
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Moitra, A., Sreenivasan, P.R., Mannan, S.L. et al. Ductile-brittle transition temperatures and dynamic fracture toughness of 9Cr-1Mo steel. Metall Mater Trans A 36, 2957–2965 (2005). https://doi.org/10.1007/s11661-005-0069-4
Received:
Issue Date:
DOI: https://doi.org/10.1007/s11661-005-0069-4