A novel monitoring system for fatigue crack length of compact tensile specimen in liquid lead-bismuth eutectic
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Fatigue strength of the structural materials of lead-cooled fast reactors (LFRs) and accelerator-driven systems (ADS) may be degraded in liquid metal (Lead or lead-bismuth eutectic (LBE)) environments. The fatigue crack growth (FCG) data of structural materials in liquid LBE are necessary for damage tolerance design, safety assessment and life management of key equipment. A novel monitoring system for fatigue crack length was designed on the compliance method and the monitor technology of crack opening displacement (COD) of CT specimens by the linear variable differential transformers (LVDT) system. It can be used to predict the crack length by monitoring the COD of CT specimens in harsh high-temperature liquid LBE using a LVDT system. The prediction accuracy of this system was verified by FCG experiments in room temperature air and liquid LBE at 150, 250 and 350 ◦C. The first results obtained in the FCG test for T91 steel in liquid LBE at 350 ◦C are presented.
Abstract
Fatigue strength of the structural materials of lead-cooled fast reactors (LFRs) and accelerator-driven systems (ADS) may be degraded in liquid metal (Lead or lead-bismuth eutectic (LBE)) environments. The fatigue crack growth (FCG) data of structural materials in liquid LBE are necessary for damage tolerance design, safety assessment and life management of key equipment. A novel monitoring system for fatigue crack length was designed on the compliance method and the monitor technology of crack opening displacement (COD) of CT specimens by the linear variable differential transformers (LVDT) system. It can be used to predict the crack length by monitoring the COD of CT specimens in harsh high-temperature liquid LBE using a LVDT system. The prediction accuracy of this system was verified by FCG experiments in room temperature air and liquid LBE at 150, 250 and 350 ◦C. The first results obtained in the FCG test for T91 steel in liquid LBE at 350 ◦C are presented.
참고문헌 (26)
- E. D. Shchukin, "Analysis of liquid metal embrittlement in materials", Mendeleev Commun, 29, pp.716~717 (2019)
- S. Bassini, "Comprehensive Nuclear Materials", pp.218~241 (2020)
- P. K. Nema, "Application of accelerators for nuclear systems : accelerator driven system(ADS)", Energy Proc, 7, pp.597~608 (2011)
- A. Alemberti, "Overview of lead-cooled fast reactor activities", Prog. Nucl. Energy, 77, pp.300~307 (2014)
- Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies - 2015 Edition, , Nuclear Energy Agency of the OECD (NEA), ~, pp.NEA–7268 (2015)
- G. N. A. Legris, "Liquid metal embrittlement of the martensitic steel 91 : influence of the chemical composition of the liquid metal. : experiments and electronic structure calculations", J. Nucl. Mater, 301, pp.70~76 (2002)
- B. Long, "Liquid Pb–Bi embrittlement effects on the T91steel after different heat treatments", J. Nucl. Mater, 377, pp.219~224 (2008)
- T. Auger, "Effect of contact conditions on embrittlement of T91 steel by lead–bismuth", J. Nucl. Mater, 335, pp.227~231 (2004)
- S. Bassini, "Material performance in lead and lead-bismuth alloy", Comprehensive Nuclear Materials, pp.218~241 (2020)
- H. Wang, "Liquid metal embrittlement of 12Cr ferritic", martensitic steel thinwalled tubes exposed to liquid lead-bismuth eutectic, 2022, pp.195, 110024~
- C. F. Old, "Liquid metal embrittlement of nuclear materials", J. Nucl. Mater, 92, pp.2~25 (1980)
- X. Gong, "Environmental degradation of structural materials in liquid lead-and lead-bismuth eutectic-cooled reactors", Prog. Mater. Sci, 126, pp.100920~ (2022)
- J. -B. Vogt, "Stability of fatigue cracks at 350 ◦C in air and in liquid metal in T91 martensitic steel", Int. J. Fatig, 130, pp.105265~ (2020)
- H. P. Seifert, "Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions", Corrosion Sci, 55, pp.61~75 (2012)
- J. A. Duff, "In situ observation of short fatigue crack propagation in oxygenated water at elevated temperature and pressure", Corrosion Sci, 68, pp.34~43 (2013)
- Mechanical, "microstructural characteristics of environmentally-assisted degradation effects of steels in lead alloys and assessment of environmental degradation effects on performance of structural and functional components of MYRRHA ADS & LFR", M. Chocholousek, 2017, MatISSE – D5.42
- A. Hojna, "On the kinetics of LME for the ferritic–martensitic steel T91 immersed in liquid PbBi eutectic", J. Nucl. Mater, 413, pp.21~29 (2011)
- C. Ye, "Brittle fracture of T91 steel in liquid lead–bismuth eutectic alloy", Nucl. Eng. Des, 280, pp.680~685 (2014)
- J. Van den Bosch, "Fracture toughness assessment of ferritic–martensitic steel in liquid lead–bismuth eutectic", J. Nucl. Mater, 385(2), pp.250~257 (2009)
- F. Ersoy, "Investigating liquid-metal embrittlement of T91steel by fracture toughness tests", J. Nucl. Mater, 472, pp.171~177 (2016)
- B. Xue, "Effect of temperature on low cycle fatigue behavior of T91 steel in liquid lead-bismuth eutectic environment at 150–550◦C", Int. J. Fatig, 167, pp.107344~ (2023)
- J. Ashok Saxena, "Review and extension of compliance information for common crack growth specimens", Int. J. Fract, 14, pp.453~468 (1978)
- "Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials, ASTM E399", ASTM, ~ (1997)
- "Standard Test Method for Measurement of Fatigue Crack Growth Rates, ASTM E647", ~ (2008)
- X. Gong, "Low cycle fatigue behavior of a modified 9Cr–1Mo ferritic–martensitic steel in lead–bismuth eutectic at 350◦C – effects of oxygen concentration in the liquid metal and strain rate", Corrosion Sci, 94, pp.377~391 (2015)
- A. Verleene, "Fatigue behavior of martensitic steel T91 at 300◦C in liquid leadbismuth eutectic", pp.2005