Creep behavior and life prediction of a reactor pressure vessel steel above phase-transformation temperature via a deformation mechanism-based creep model
Chuanyang Lu
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
MOE Key Laboratory of Pressure Systems and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai, China
Search for more papers by this authorPeng Wang
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorSilu Zheng
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorXijia Wu
Structures and Materials Performance Laboratory, Institute for Aerospace Research, National Research Council Canada, Ottawa, Ontario, Canada
Search for more papers by this authorRong Liu
Department of Mechanical and Aerospace Engineering, Carleton University, Ottawa, Ontario, Canada
Search for more papers by this authorCorresponding Author
Yanming He
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Correspondence
Yanming He, Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou 310014, China.
Email: [email protected]
Search for more papers by this authorJianguo Yang
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorZengliang Gao
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorShan-Tung Tu
MOE Key Laboratory of Pressure Systems and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai, China
Search for more papers by this authorChuanyang Lu
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
MOE Key Laboratory of Pressure Systems and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai, China
Search for more papers by this authorPeng Wang
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorSilu Zheng
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorXijia Wu
Structures and Materials Performance Laboratory, Institute for Aerospace Research, National Research Council Canada, Ottawa, Ontario, Canada
Search for more papers by this authorRong Liu
Department of Mechanical and Aerospace Engineering, Carleton University, Ottawa, Ontario, Canada
Search for more papers by this authorCorresponding Author
Yanming He
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Correspondence
Yanming He, Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou 310014, China.
Email: [email protected]
Search for more papers by this authorJianguo Yang
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorZengliang Gao
Institute of Process Equipment and Control Engineering, College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education, Zhejiang University of Technology, Hangzhou, China
Search for more papers by this authorShan-Tung Tu
MOE Key Laboratory of Pressure Systems and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai, China
Search for more papers by this authorAbstract
For nuclear power generation as a carbon-neutral energy source, in-vessel retention (IVR) must be implemented to maintain the structural integrity of nuclear reactor pressure vessel (RPV) for more than 72 h under severe accidental conditions. This technology requires accurate prediction of creep deformation and life of RPV material being operated under pressure and extremely high-temperature gradient. The current work develops a simplified deformation-mechanism-based true-stress (DMTS) model for creep behavior/life-prediction of SA508 Gr.3 steel, a typical RPV material, above the phase transformation temperatures (800–1000°C). This model is used to evaluate the time to specific creep strain (t3% and t5%) and rupture (tr), in comparison with popular empirical methods such as Orr–Sherby–Dorn (OSD) and Larson–Miller (LM). The simplified DMTS model achieves an excellent agreement with the experimental observations. The controlling deformation mechanisms are also discussed by metallurgical examinations, which provide the physical premise for the model development and application.
Highlights
- A simplified deformation-mechanism-based true-stress (DMTS) creep model was proposed.
- This model predicted the creep-strain time and life of SA508 Gr. 3 at 800–1000°C.
- The prediction accuracy of simplified DMTS was compared with LM and OSD methods.
- The dominant creep deformation mechanism was dislocation climb-plus-glide.
CONFLICT OF INTEREST STATEMENT
The authors declared that they have no conflicts of interest to this work.
Open Research
DATA AVAILABILITY STATEMENT
The raw/processed data will be made available on request.
REFERENCES
- 1 International Atomic Energy Agency. Nuclear technology review 2021. IAEA; 2021.
- 2 International Atomic Energy Agency. Nuclear power reactors in the world. IAEA; 2022.
- 3Giri A. Assessment of reactor vessel integrity. Nucl Eng des. 2002; 221(1–3): 23-53.
- 4Chu TY, Bainbridge BL, Simpson RB, Bentz JH. Ex-vessel boiling experiments: laboratory-and reactor-scale testing of the flooded cavity concept for in-vessel core retention part I: observation of quenching of downward-facing surfaces. Nucl Eng des. 1997; 169(1-3): 89-99.
- 5Sehgal BR, Nourgaliev RR, Dinh TN. Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment. Nucl Eng des. 2002; 211(2-3): 173-187.
- 6Koundy V, Caroli C, Nicolas L, Matheron P, Gentzbittel JM, Coret M. Study of tearing behaviour of a PWR reactor pressure vessel lower head under severe accident loadings. Nucl Eng des. 2008; 238(9): 2411-2419.
- 7Thinnes GL, Korth GE, Chavez SA, Walker TJ. High-temperature creep and tensile data for pressure vessel steels SA533B1 and SA508-CL2. Nucl Eng des. 1994; 148(2-3): 343-350.
- 8Willschuetz HG, Altstadt E, Sehgal BR, Weiss FP. Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure. Ann Nucl Energy. 2003; 30(10): 1033-1063.
- 9Xie LJ, Ren X, Shen MX, Tu LQ. Parameter correlation of high-temperature creep constitutive equation for RPV metallic materials. J Nucl Mater. 2015; 465: 196-203.
- 10Xie LJ, Ning D, Yang YZ. Experimental study on creep characterization and lifetime estimation of RPV material at 723-1023K. J Mater Eng Perform. 2017; 26(2): 1-9.
- 11Xie ZG, He YM, Yang JG, Li XQ, Lu CY, Gao ZL. Microscopic damage mechanism of SA508 Gr3 steel in ultra-high temperature creep. J Iron Steel Res Int. 2018; 025(4): 453-459.
10.1007/s42243-018-0055-x Google Scholar
- 12Lu CY, He YM, Yang JG, Zheng WJ, Xie ZG, Gao ZL. An investigation of phase transition on the microstructural characteristic and creep behavior for the SA508 gr. 3 steel used for nuclear reactor pressure vessels. Mater Sci Eng A. 2017; 711: 659-669.
- 13Loktionov V, Mukhtarov E, Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification. Nucl Eng des. 2018; 326: 320-332.
- 14Dunand D, Han B, Jansen AM. Monkman-grant analysis of creep fracture in dispersion-strengthened and particulate-reinforced aluminum. Metall Mater Trans A. 1999; 30(13): 829-838.
10.1007/s11661-999-1016-6 Google Scholar
- 15Maruyama K, Abe F, Sato H, Shimojo J, Sekido N, Yoshimi K. On the physical basis of a Larson-miller constant of 20. Int J Pres Ves pip. 2017; 159: 93-100.
- 16Wang RZ, Gu HH, Zhu SP, et al. A data-driven roadmap for creep-fatigue reliability assessment and its implementation in low-pressure turbine disk at elevated temperatures. Reliab Eng Syst Safe. 2022; 225:108523.
- 17Zhang W, Zhang T, Wang X, Ji Y, Gong J. The correlation between prior fatigue damage and remaining creep properties in a high chromium steel welded joint. Mater Sci Eng A. 2020; 790:139717.
- 18Zhao J, Gong J, Saboo A, Dunand DC, Olson GB. Dislocation-based modeling of long-term creep behaviors of grade 91 steels. Acta Mater. 2018; 149: 19-28.
- 19Zhao L, Alang N, Nikbin K. Investigating creep rupture and damage behaviour in notched P92 steel specimen using a microscale modelling approach. Fatigue Fract Eng M. 2018; 41(2): 456-472.
- 20Atkins AG. Deformation-mechanism maps (the plasticity and creep of metals and ceramics). Pergamon Press; 1982.
- 21Wu X. Deformation and evolution of life in crystalline materials: an integrated creep-fatigue theory. Pergamon Press; 2019.
10.1201/b22348 Google Scholar
- 22Wu X, Williams S, Gong D. A true-stress creep model based on deformation mechanisms for polycrystalline materials. J Mater Eng Perform. 2012; 21(11): 2255-2262.
- 23Zhang XZ, Wu XJ, Liu R, Liu J, Yao MX. Deformation-mechanism-based modeling of creep behavior of modified 9Cr-lMo steel. Mater Sci Eng A. 2017; 689: 345-352.
- 24Xiao B, Xu L, Zhao L, Jing H, Han Y. Deformation-mechanism-based creep model and damage mechanism of G115 steel over a wide stress range. Mater Sci Eng A. 2019; 743: 280-293.
- 25Lu CY, Wu XJ, He YM, Gao ZL, Yang JG. Deformation mechanism-based true-stress creep model for SA508 gr.3 steel over the temperature range of 450–750 °C. J Nucl Mater. 2019; 526:151776.
- 26Lu CY, He YM, Gao ZL, Yang JG, Jin WY, Xie ZG. Microstructural evolution and mechanical characterization for the A508–3 steel before and after phase transition. J Nucl Mater. 2017; 495: 103-110.
- 27 International A. ASTM E139–11. Standard Test Methods for Conducting Creep, Creep-Rupture, and Stress-Rupture Tests of Metallic Materials; 2018.
- 28Gao ZL, Lu CY, He YM, et al. Influence of phase transformation on the creep deformation mechanism of SA508 gr. 3 steel for nuclear reactor pressure vessels. J Nucl Mater. 2019; 519: 292-301.
- 29Mukherjee AK, Bird JE, Dorn JE. Experimental correlations for high-temperature creep. Trans ASM. 1968; 62: 155-179.
- 30Xiao B, Xu LY, Zhao L, Jing HY, Han YD. Creep properties, creep deformation behavior, and microstructural evolution of 9Cr-3W-3Co-1CuVNbB martensite ferritic steel. Mater Sci Eng A. 2018; 711: 434-447.
- 31Kweon HD, Kim JW, Song O, Oh D. Determination of true stress-strain curve of type 304 and 316 stainless steels using a typical tensile test and finite element analysis. Nucl Eng Technol. 2021; 53(2): 647-656.
- 32Li YF, Zhou JH, Liu YF, et al. Microstructural evolution and mechanical characterization for the AlCoCrFeNi2.1 eutectic high-entropy alloy under different temperatures. Fatigue Fract Eng M. 2023; 46(5): 1881-1892.
- 33Wu XJ, Koul AK. Grain boundary sliding in the presence of grain boundary precipitates during transient creep. Metall Mater Trans A. 1995; 26(4): 905-914.
- 34Shrestha T, Basirat M, Charit I, Potirniche GP, Rink KK, Sahaym U. Creep deformation mechanisms in modified 9Cr–1Mo steel. J Nucl Mater. 2012; 423(1-3): 110-119.
- 35Chokshi AH. High temperature deformation in fine grained high entropy alloys. Mater Chem Phys. 2017; 210: 152-161.
- 36Wilshire B. Observations, theories, and predictions of high-temperature creep behavior. Metall Mater Trans A. 2002; 33(2): 241-248.
- 37Deck CP, Vecchio K. Prediction of carbon nanotube growth success by the analysis of carbon–catalyst binary phase diagrams. Carbon. 2006; 44: 267-275.
- 38Lu CY, Qin ZL, Wang SY, et al. Uncovering the high-temperature microstructural evolution and creep-fatigue damage mechanism of CMSX-4 brazed joints. Int J Fatigue. 2023; 173:107681.
- 39Lu CY, Zhang CY, Xu HT, et al. Constructing a heterogeneous interlayer in relieving the residual stresses for the AlN/cu brazed joint used in IGBT. Mater Charact. 2023; 199:112759.
- 40Ma XL, Huang CX, Moering J, et al. Mechanical properties of copper/bronze laminates: role of interfaces. Acta Mater. 2016; 116: 43-52.
- 41Dahlberg CF, Saito Y, Ztop MS, Kysar JW. Geometrically necessary dislocation density measurements at a grain boundary due to wedge indentation into an aluminum Bicrystal. J Mech Phys Solids. 2017; 105: 131-149.
- 42Li C, Han L, Yan G, Liu Q, Luo X, Gu J. Time-dependent temper embrittlement of reactor pressure vessel steel: correlation between microstructural evolution and mechanical properties during tempering at 650°C. J Nucl Mater. 2016; 480: 344-354.
- 43Zhao P, Xuan FZ, Wang C. A physically-based model of cyclic responses for martensitic steels with the hierarchical lath structure under different loading modes. J Mech Phys Solids. 2019; 124: 555-576.
- 44Hales R. A method of creep damage summation based on accumulated strain for the assessment of creep-fatigue endurance. Fatigue Fract Eng M. 1983; 6(2): 121-135.
- 45Ainsworth R. R5: assessment procedure for the high temperature response of structures. British energy generation Ltd; 2003.
- 46Spindler MW. The prediction of creep damage in type 347 weld metal. Part I: the determination of material properties from creep and tensile tests. Int J Pres Ves pip. 2005; 82(3): 175-184.
- 47Spindler MW, Payten WM. Advanced ductility exhaustion methods for the calculation of creep damage during creep-fatigue cycling. Creep-Fatigue Interactions: Test Methods and Models. San Antonio TX; 2010, 8, 7, 103806.