Abstract:P280GH carbon manganese steels used for the nuclear steam system and auxiliary system pipes in pressurized water reactor nuclear power plant are susceptible to thermal aging brittleness during long-term service at its working temperature from 280 to 350 ℃. In order to investigate its thermal aging behavior, P280GH carbon manganese steels have been thermally aged at 400 ℃ for up to 10 000 h. The micro-hardness of ferrite and pearlite phases, conventional tensile properties and impact properties at different aging duration have been measured. The results show that the micro-hardness of ferrite and pearlite gradually decreases with increasing thermal aging time. The tensile strength and yield strength increase within 300 h and then progressively and slightly decrease after 300 h with the long aging time, respectively. The charpy impact energy slightly decreases with the long aging time. The changes of all the above mechanical properties of P280GH carbon manganese steels are associated with the changes of the pearlite morphologies, dislocation configurations in ferrite and precipitates after different thermal aging time.
收稿日期: 2017-02-23
出版日期: 2017-09-07
引用本文:
于 辉,翟建伟,张超凡,刘帅帅,刘利刚. 核岛用P280GH碳锰钢热老化的组织和性能[J]. 钢铁, 2017, 52(9): 66-72.
YU Hui,ZHAI Jian-wei,ZHANG Chao-fan,LIU Shuai-shuai,LIU Li-gang. Microstructures and properties of nuclear carbon manganese steels P280GH after accelerated aging. Iron and Steel, 2017, 52(9): 66-72.
YAN Qiang, WANG Anjian, WANG Gaoshang, et al. Nuclear power development in China and uranium demand forecast: Based on analysis of global current situation[J]. Progress in Nuclear Energy, 2011, 53(6): 742-747.
[1]
YAN Qiang, WANG Anjian, WANG Gaoshang, et al. Nuclear power development in China and uranium demand forecast: Based on analysis of global current situation[J]. Progress in Nuclear Energy, 2011, 53(6): 742-747.
[2]
Saha P, Aksan N, Andersen J, et al. Issues and future direction of thermal-hydraulics research and development in nuclear power reactors[J]. Nuclear Engineering and Design, 2013, 264(11): 3-23.
[2]
Saha P, Aksan N, Andersen J, et al. Issues and future direction of thermal-hydraulics research and development in nuclear power reactors[J]. Nuclear Engineering and Design, 2013, 264(11): 3-23.
Chopra O K, Chung H M. Aging of cast duplex stainless steels in LWR systems [J]. Nuclear Engineering and Design, 1985, 89(2-3): 305-318.
[4]
Chopra O K, Chung H M. Aging of cast duplex stainless steels in LWR systems [J]. Nuclear Engineering and Design, 1985, 89(2-3): 305-318.
[5]
Bethmont M, Meyzaud Y, Soulat P. Properties of cast austenitie materials for light water reactors[J]. International Journal of Pressure Vessels and Piping, 1996, 65(3): 221-229.
[5]
Bethmont M, Meyzaud Y, Soulat P. Properties of cast austenitie materials for light water reactors[J]. International Journal of Pressure Vessels and Piping, 1996, 65(3): 221-229.
[6]
J K Sahu, U Krupp, R N Ghosh, et al. Effect of 475℃ embrittlement on the mechanical properties of duplex stainless steel[J]. Material Science & Engineering A, 2009, 508(1-2): 1-14.
[6]
J K Sahu, U Krupp, R N Ghosh, et al. Effect of 475℃ embrittlement on the mechanical properties of duplex stainless steel[J]. Material Science & Engineering A, 2009, 508(1-2): 1-14.
[7]
J D Tucker, M K Miller, GA Young. Assessment of thermal embrittlement in duplex stainless steels 2003 and 2205 for nuclear power applications[J]. Acta Materialia, 2015, 87: 15-24.
[7]
J D Tucker, M K Miller, GA Young. Assessment of thermal embrittlement in duplex stainless steels 2003 and 2205 for nuclear power applications[J]. Acta Materialia, 2015, 87: 15-24.
[8]
J Zhou, J Odqvist, M Thuvander, et al. Concurrent phase separation and clustering in the ferrite phase during low temperature stress aging of duplex stainless steel weldments[J]. Acta Materialia, 2012, 60(16): 5818-5827.
[8]
J Zhou, J Odqvist, M Thuvander, et al. Concurrent phase separation and clustering in the ferrite phase during low temperature stress aging of duplex stainless steel weldments[J]. Acta Materialia, 2012, 60(16): 5818-5827.
[9]
H C Wu, B Yang, S L Wang, et al. Effect of thermal aging on corrosion fatigue of Z3CN20.09M duplex stainless steel in high temperature water[J]. Material Science & Engineering A, 2016, 655: 183-192.
[9]
H C Wu, B Yang, S L Wang, et al. Effect of thermal aging on corrosion fatigue of Z3CN20.09M duplex stainless steel in high temperature water[J]. Material Science & Engineering A, 2016, 655: 183-192.
[10]
CA Della Rovere, FS Santos, R Silva, et al. Influence of long-term low-temperature aging on the microhardness and corrosion properties of duplex strainless steel[J]. Corrosion Science, 2013, 68(1): 84-90.
[10]
CA Della Rovere, FS Santos, R Silva, et al. Influence of long-term low-temperature aging on the microhardness and corrosion properties of duplex strainless steel[J]. Corrosion Science, 2013, 68(1): 84-90.
[11]
R Silva, L F S Baroni, MBR Silva, et al. Effect of thermal aging at 475℃ on the properties of lean duplex strainless steel 2101[J]. Materials Characterization, 2016, 114: 211-217.
[11]
R Silva, L F S Baroni, MBR Silva, et al. Effect of thermal aging at 475℃ on the properties of lean duplex strainless steel 2101[J]. Materials Characterization, 2016, 114: 211-217.
[12]
K Chandra, V Kain, V Bhutani, et al. Low temperature thermal aging of austenitic stainless steel welds: Kinetics and effects on mechanical properties[J]. Material Science & Engineering A, 2012, 534(1): 163-175.
[12]
K Chandra, V Kain, V Bhutani, et al. Low temperature thermal aging of austenitic stainless steel welds: Kinetics and effects on mechanical properties[J]. Material Science & Engineering A, 2012, 534(1): 163-175.
[13]
T Nishizawa, M Hasebe, M Ko. Thermodynamic analysis of solubility and miscibility gap in ferromagnetic alpha iron alloys[J]. Acta Metallurgica, 1979, 27(5): 817-828.
[13]
T Nishizawa, M Hasebe, M Ko. Thermodynamic analysis of solubility and miscibility gap in ferromagnetic alpha iron alloys[J]. Acta Metallurgica, 1979, 27(5): 817-828.
[14]
T J Nichol, A Datta, G Aggen. Embrittlement of ferritic stainless steels[J]. Metallurgical and Materials Transactions A, 1980, 11(4): 573-585.
[14]
T J Nichol, A Datta, G Aggen. Embrittlement of ferritic stainless steels[J]. Metallurgical and Materials Transactions A, 1980, 11(4): 573-585.
[15]
S S Brenner, M K Miller, W A Soffa. Spinodal decomposition of iron-32 at.% chromium at 470℃[J]. Scripta Metallurgica, 1982, 16(7): 831-836.
[15]
S S Brenner, M K Miller, W A Soffa. Spinodal decomposition of iron-32 at.% chromium at 470℃[J]. Scripta Metallurgica, 1982, 16(7): 831-836.
[16]
Wei Wang, Shaojun Liu, Gang Xu, et al. Effect of Thermal Aging on Microstructure and Mechanical Properties of China Low-Activation Martensitic Steel at 550 ℃[J]. Nuclear Engineering and Technology, 2016, 48(2): 518-524.
[16]
Wei Wang, Shaojun Liu, Gang Xu, et al. Effect of Thermal Aging on Microstructure and Mechanical Properties of China Low-Activation Martensitic Steel at 550 ℃[J]. Nuclear Engineering and Technology, 2016, 48(2): 518-524.
T Goto, T Naito, T Yamaoka. A study on NDE method of thermal aging of cast duplex stainless steels[J]. Nuclear Engineering and Design, 1998, 182(2): 181-192.
T Goto, T Naito, T Yamaoka. A study on NDE method of thermal aging of cast duplex stainless steels[J]. Nuclear Engineering and Design, 1998, 182(2): 181-192.
H M Chung. Aging and Life Prediction of Cast Duplex Stainless Steel Components [J]. International Journal of Pressure Vessels and Piping, 1992, 50(1-3): 179-213.
[23]
H M Chung. Aging and Life Prediction of Cast Duplex Stainless Steel Components [J]. International Journal of Pressure Vessels and Piping, 1992, 50(1-3): 179-213.