[1] Schaefer, A. O. Symposium on structural materials for service at elevated temperatures in nuclear power generation, American Society of Mechanical Engineering winter annual meeting, Houston, USA, November 30-Desember 3, 1975: 375-385.
[2] A Chatterjee, D Chakrabarti, A Moitra, et al. Effect of normalization temperatures on ductile–brittle transition temperature of a modified 9Cr–1Mo steel. Materials Science and Engneering: A, 2014, A618: 219-231.
[3] R L Klueh, A T Nelson. Ferritic/martensitic steels for next-generation reactors. Journal of Nuclear Materials, 2007, 371: 37-52.
[4] B N Singh, J H Evans. Significant differences in defect accumulation behaviour between fcc and bcc crystals under cascade damage conditions. Journal of Nuclear Materials, 1995,226: 277-285.
[5] B Raj, S Saroja, K Laha, et al. Methods to overcome embrittlement problem in 9Cr-1Mo ferritic steel and its weldment. Journal of Materials Science, 2009, 44: 2239-2246.
[6] F Masuyama. History of power plants and progress in heat resistant steels. ISIJ International, 2001, 41: 612-625.
[7] R L Klueh. Elevated emperature ferrtic and martensitic steels and their application to future nuclear reactors. Internatonal Materials Reviews, 2005, 50: 287-310.
[8] R Viswanathan, W Bakker. Materials for ultrasupercritical coal power plants-boiler materials: Part 1. Journal of Materials Engineering and Performance, 2001, 10: 81-95.
[9] R L Klueh, D J Alexander. Impact Behavior of 9Cr-1MoVNb and 12Cr-1MoVW steels Irradiated in HFIR. Journal of Nuclear Materials, 1991, 179-181: 733-736.
[10] C Wassilew, K Ehrlich. Effect of neutron irradiation on the dynamic fracture toughness behavior of the 12% Cr steel MANET-I investigated using subsize V-notch specimens. Journal of Nuclear Materials, 1992, 191-194: 850-854.
[11] Y Dai, P Marmy. Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ target-3. Journal of Nuclear Materials, 2005, 343(1-3): 247-252.
[12] R L Klueh, J J Kai, D J Alexander. Microstructure-mechanical properties correlation of irradiated conventional and reduced-activation martensitic steels. Journal of Nuclear Materials, 1995, 225: 175-186.
[13] D S Gelles. Microstructural examination of commercial ferritic alloys at 200 dpa. Journal of Nuclear Materials, 1996, 233(1): 293-298.
[14] C Y Yang, Y K Luam, D Z Li, et al.. Effects of rare earth elements on inclusions and impact toughness of high-carbon chromium bearing steel. Journal of Materials Science Technology, 2019, 35: 1298-1308.
[15] Q Y Huang. Development status of CLAM steel for fusion application. Journal of Nuclear Materials, 2014, 455: 649–654.
[16] P Jung, H Klein. Segregation in DIN 1.4914 martensitic stainless steel under proton irradiation. Journal of Nuclear Materials, 1991, 182: 1-5.
[17] T. Watanabe, S. Tsurekawa. Toughening of brittle materials by grain boundary engineering. Materials Science and Engneering: A, 2004, 387-389: 447-455.
[18] S.A. Bashu, K. Singh, M.S. Rawat. Effect of heat treatment on mechanical properties and fracture behaviour of a 12CrMoV steel. Materials Science and Engneering: A, 1990, 127: 7-15.
[19] T. Karthikeyan, V.T. Paul, S. Saroja, A. Moitra, G. Sasikala, M. Vijayalakshmi. Grain refinement to improve impact toughness in 9Cr–1Mo steel through a double austenitization treatment. Journal of Nuclear Materials, 2011, 419: 256-262.
[20] A. Chatterjee, A. Moitra, A.K. Bhaduri, D. Chakrabarti, R. Mitra, Effect of Heat Treatment on Ductile-Brittle Transition Behaviour of 9Cr-1Mo Steel. Procedia Engineering, 2014, 86: 287-294.
[21] J.B. Zhang, F. Liu, D. Fan, Z.Y. Zhen. Effect of Heat Treatment on Delta-ferritie and Impact Toughness of P91 Heat-resistant Steel. Transactions of Materials and Heat Treatment, 2017, 38: 108-113. (in Chinese)
[22] Chinese National Standard Committee. GB/T 5310-2008, Seamless steel tubes and pipes for high pressure boiler. Beijing: Standards Press of China, 2008. (in Chinese)
[23] R L Klueh., N Hashimoto, R F Buck et al. A potential new ferritic/martensitic steel for fusion applications. Journal of Nuclear Materials, 2000,283-287:697-701.
[24] N.Z. Gutiérrez, H. De Cicco, J. Marrero, C.A. Danón, M.I. Luppo. Evolution of precipitated phases during prolonged tempering in a 9%Cr1%MoVNb ferritic–martensitic steel: Influence on creep performance. Materials Science and Engneering: A, 2011, 528: 4019-4029.
[25] C.X. Liu, D.T. Zhang, Y.C. Liu, Q. Wang, Z.S. Yan, Investigation on the precipitation behavior of M3C phase in T91 ferritic steels. Nuclear Engineering and Design, 2011, 241: 2411-2415.
[26] W.B. Jones, C.R. Hills, D.H. Polonis, Microstructural evolution of modified 9Cr-1Mo steel. Metallurgical Transactions A, 1991, 22(5): 1049-1058.
[27] C Xiang. Alloy Steels. Beijing: Metallurgy Press, 1999. (in Chinese)
[28] D. Lonsdale, P.E.J. Flewitt, D, Lonsdale, P, et al. The role of grain size on the ductile-brittle transition of a 2.25 Pct Cr-1 Pct Mo steel. Metallurgical Transactions A, 1978, 9: 1619-1623.
[29] T. Hanamura, F. Yin, K. Nagai. Ductile-brittle transition temperature of ultrafine ferrite/cementite microstructure in a low carbon steel controlled by effective grain size. ISIJ International, 2004, 44(3): 610-617.
[30] S.H. Kim, W.S. Ryn, I.H. Kuk, Nucl. Eng. Technol. 31 (1999) 561-571.
[31] E.A. Little, D.R. Harries, F.B. Pickering, in: S.F. Pugh, E.A. Little (Eds.), Proc. Int. Conf. Ferritic Steels for Fast Reactor Steam Generator, British Nuclear Energy Society, London, 1978, pp. 136-144.
[32] A.H. Cai, Y. Zhou, J.Y. Tan, Y. Luo, T.L. Li, M. Chen, W.K. An, Optimization of composition of heat-treated chromium white cast iron casting by phosphate graphite mold. Journal of Alloys and Compound, 2008, 466: 273-280.
[33] R.C. Fan, M. Gao, Y.C. Ma, X.D. Zha, X.C. Hao, K. Liu. Effects of Heat Treatment and Nitrogen on Microstructure and Mechanical Properties of Cr12NiMo Martensitic Stainless Steel. Journal of Materials Science Technology, 2012, 28: 1059-1066.
[34] S.J. Kim, Y.G. Cho, C.S. Oh, D.E. Kim, M.B. Moon, H.N. Han. Development of a dual phase steel using orthogonal design method. Materials and Design, 2009, 30: 1251-1257.
[35] Y Li, Q Huang, Y Wu, et al. Mechanical properties and microstructures of China low activation martensitic steel compared with JLF-1. Journal of Nuclear Materials, 2007, 367–370: 117–121.
[36] A Moitra, P Parameswaran, P R Sreenivasan, et al. A toughness study of the weld heat-affected zone of a 9Cr–1Mo steel. Materials Characterization, 2002, 48: 55–61.
[37] K H Hartman, H D Kunze, L W Meyer. Shock Waves and High-Strain-Rate Phenomena in Metals. Boston, MA: Springer, 1980.
[38] C Y Gao, L C Zhang. A constitutive model for dynamic plasticity of FCC metals. Materials Science and Engneering: A, 2010, 527: 3138-3143.
[39] C Pandey, A Giri, M M Mahapatra. Evolution of phases in P91 steel in various heat treatment conditions and their effect on microstructure stability and mechanical properties. Materials Science and Engneering: A, 2016, 664: 58-74.
[40] H Sakasegawa, T Hirose, A Kohyama, et al. Effects of precipitation morphology on toughness of reduced activation ferritic/martensitic steels. Journal of Nuclear Materials, 2002, 307-311: 490-494.
[41] S T Rolfe, J M Barsom. Fracture and fatigue control in structures, Application of Fracture Mechanics, Upper Saddle River NJ: Prentice-hall, Inc., 1977.
[42] G T Hahn, M F Kanninen, A R Rosenfield. Fracture Toughness of Materials. Annual Review of Materials Research, 1972, 2(1): 381-404.
[1] Schaefer, A. O. Symposium on structural materials for service at elevated temperatures in nuclear power generation, American Society of Mechanical Engineering winter annual meeting, Houston, USA, November 30-Desember 3, 1975: 375-385.
[2] A Chatterjee, D Chakrabarti, A Moitra, et al. Effect of normalization temperatures on ductile–brittle transition temperature of a modified 9Cr–1Mo steel. Materials Science and Engneering: A, 2014, A618: 219-231.
[3] R L Klueh, A T Nelson. Ferritic/martensitic steels for next-generation reactors. Journal of Nuclear Materials, 2007, 371: 37-52.
[4] B N Singh, J H Evans. Significant differences in defect accumulation behaviour between fcc and bcc crystals under cascade damage conditions. Journal of Nuclear Materials, 1995,226: 277-285.
[5] B Raj, S Saroja, K Laha, et al. Methods to overcome embrittlement problem in 9Cr-1Mo ferritic steel and its weldment. Journal of Materials Science, 2009, 44: 2239-2246.
[6] F Masuyama. History of power plants and progress in heat resistant steels. ISIJ International, 2001, 41: 612-625.
[7] R L Klueh. Elevated emperature ferrtic and martensitic steels and their application to future nuclear reactors. Internatonal Materials Reviews, 2005, 50: 287-310.
[8] R Viswanathan, W Bakker. Materials for ultrasupercritical coal power plants-boiler materials: Part 1. Journal of Materials Engineering and Performance, 2001, 10: 81-95.
[9] R L Klueh, D J Alexander. Impact Behavior of 9Cr-1MoVNb and 12Cr-1MoVW steels Irradiated in HFIR. Journal of Nuclear Materials, 1991, 179-181: 733-736.
[10] C Wassilew, K Ehrlich. Effect of neutron irradiation on the dynamic fracture toughness behavior of the 12% Cr steel MANET-I investigated using subsize V-notch specimens. Journal of Nuclear Materials, 1992, 191-194: 850-854.
[11] Y Dai, P Marmy. Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ target-3. Journal of Nuclear Materials, 2005, 343(1-3): 247-252.
[12] R L Klueh, J J Kai, D J Alexander. Microstructure-mechanical properties correlation of irradiated conventional and reduced-activation martensitic steels. Journal of Nuclear Materials, 1995, 225: 175-186.
[13] D S Gelles. Microstructural examination of commercial ferritic alloys at 200 dpa. Journal of Nuclear Materials, 1996, 233(1): 293-298.
[14] C Y Yang, Y K Luam, D Z Li, et al.. Effects of rare earth elements on inclusions and impact toughness of high-carbon chromium bearing steel. Journal of Materials Science Technology, 2019, 35: 1298-1308.
[15] Q Y Huang. Development status of CLAM steel for fusion application. Journal of Nuclear Materials, 2014, 455: 649–654.
[16] P Jung, H Klein. Segregation in DIN 1.4914 martensitic stainless steel under proton irradiation. Journal of Nuclear Materials, 1991, 182: 1-5.
[17] T. Watanabe, S. Tsurekawa. Toughening of brittle materials by grain boundary engineering. Materials Science and Engneering: A, 2004, 387-389: 447-455.
[18] S.A. Bashu, K. Singh, M.S. Rawat. Effect of heat treatment on mechanical properties and fracture behaviour of a 12CrMoV steel. Materials Science and Engneering: A, 1990, 127: 7-15.
[19] T. Karthikeyan, V.T. Paul, S. Saroja, A. Moitra, G. Sasikala, M. Vijayalakshmi. Grain refinement to improve impact toughness in 9Cr–1Mo steel through a double austenitization treatment. Journal of Nuclear Materials, 2011, 419: 256-262.
[20] A. Chatterjee, A. Moitra, A.K. Bhaduri, D. Chakrabarti, R. Mitra, Effect of Heat Treatment on Ductile-Brittle Transition Behaviour of 9Cr-1Mo Steel. Procedia Engineering, 2014, 86: 287-294.
[21] J.B. Zhang, F. Liu, D. Fan, Z.Y. Zhen. Effect of Heat Treatment on Delta-ferritie and Impact Toughness of P91 Heat-resistant Steel. Transactions of Materials and Heat Treatment, 2017, 38: 108-113. (in Chinese)
[22] Chinese National Standard Committee. GB/T 5310-2008, Seamless steel tubes and pipes for high pressure boiler. Beijing: Standards Press of China, 2008. (in Chinese)
[23] R L Klueh., N Hashimoto, R F Buck et al. A potential new ferritic/martensitic steel for fusion applications. Journal of Nuclear Materials, 2000,283-287:697-701.
[24] N.Z. Gutiérrez, H. De Cicco, J. Marrero, C.A. Danón, M.I. Luppo. Evolution of precipitated phases during prolonged tempering in a 9%Cr1%MoVNb ferritic–martensitic steel: Influence on creep performance. Materials Science and Engneering: A, 2011, 528: 4019-4029.
[25] C.X. Liu, D.T. Zhang, Y.C. Liu, Q. Wang, Z.S. Yan, Investigation on the precipitation behavior of M3C phase in T91 ferritic steels. Nuclear Engineering and Design, 2011, 241: 2411-2415.
[26] W.B. Jones, C.R. Hills, D.H. Polonis, Microstructural evolution of modified 9Cr-1Mo steel. Metallurgical Transactions A, 1991, 22(5): 1049-1058.
[27] C Xiang. Alloy Steels. Beijing: Metallurgy Press, 1999. (in Chinese)
[28] D. Lonsdale, P.E.J. Flewitt, D, Lonsdale, P, et al. The role of grain size on the ductile-brittle transition of a 2.25 Pct Cr-1 Pct Mo steel. Metallurgical Transactions A, 1978, 9: 1619-1623.
[29] T. Hanamura, F. Yin, K. Nagai. Ductile-brittle transition temperature of ultrafine ferrite/cementite microstructure in a low carbon steel controlled by effective grain size. ISIJ International, 2004, 44(3): 610-617.
[30] S.H. Kim, W.S. Ryn, I.H. Kuk, Nucl. Eng. Technol. 31 (1999) 561-571.
[31] E.A. Little, D.R. Harries, F.B. Pickering, in: S.F. Pugh, E.A. Little (Eds.), Proc. Int. Conf. Ferritic Steels for Fast Reactor Steam Generator, British Nuclear Energy Society, London, 1978, pp. 136-144.
[32] A.H. Cai, Y. Zhou, J.Y. Tan, Y. Luo, T.L. Li, M. Chen, W.K. An, Optimization of composition of heat-treated chromium white cast iron casting by phosphate graphite mold. Journal of Alloys and Compound, 2008, 466: 273-280.
[33] R.C. Fan, M. Gao, Y.C. Ma, X.D. Zha, X.C. Hao, K. Liu. Effects of Heat Treatment and Nitrogen on Microstructure and Mechanical Properties of Cr12NiMo Martensitic Stainless Steel. Journal of Materials Science Technology, 2012, 28: 1059-1066.
[34] S.J. Kim, Y.G. Cho, C.S. Oh, D.E. Kim, M.B. Moon, H.N. Han. Development of a dual phase steel using orthogonal design method. Materials and Design, 2009, 30: 1251-1257.
[35] Y Li, Q Huang, Y Wu, et al. Mechanical properties and microstructures of China low activation martensitic steel compared with JLF-1. Journal of Nuclear Materials, 2007, 367–370: 117–121.
[36] A Moitra, P Parameswaran, P R Sreenivasan, et al. A toughness study of the weld heat-affected zone of a 9Cr–1Mo steel. Materials Characterization, 2002, 48: 55–61.
[37] K H Hartman, H D Kunze, L W Meyer. Shock Waves and High-Strain-Rate Phenomena in Metals. Boston, MA: Springer, 1980.
[38] C Y Gao, L C Zhang. A constitutive model for dynamic plasticity of FCC metals. Materials Science and Engneering: A, 2010, 527: 3138-3143.
[39] C Pandey, A Giri, M M Mahapatra. Evolution of phases in P91 steel in various heat treatment conditions and their effect on microstructure stability and mechanical properties. Materials Science and Engneering: A, 2016, 664: 58-74.
[40] H Sakasegawa, T Hirose, A Kohyama, et al. Effects of precipitation morphology on toughness of reduced activation ferritic/martensitic steels. Journal of Nuclear Materials, 2002, 307-311: 490-494.
[41] S T Rolfe, J M Barsom. Fracture and fatigue control in structures, Application of Fracture Mechanics, Upper Saddle River NJ: Prentice-hall, Inc., 1977.
[42] G T Hahn, M F Kanninen, A R Rosenfield. Fracture Toughness of Materials. Annual Review of Materials Research, 1972, 2(1): 381-404.