Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Effect of Loading Rate on the Fracture Behavior of Nuclear Piping Materials Under Cyclic Loading Conditions

  • Kim, Jin Weon (Department of Nuclear Engineering, Chosun University) ;
  • Choi, Myung Rak (Department of Nuclear Engineering, Chosun University) ;
  • Kim, Yun Jae (Department of Mechanical Engineering, Korea University)
  • Received : 2016.03.12
  • Accepted : 2016.06.02
  • Published : 2016.12.25
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Abstract

This study investigated the loading rate effect on the fracture resistance under cyclic loading conditions to understand clearly the fracture behavior of piping materials under seismic conditions. J-R fracture toughness tests were conducted under monotonic and cyclic loading conditions at various displacement rates at room temperature and the operating temperature of nuclear power plants (i.e., $316^{\circ}C$). SA508 Gr.1a low-alloy steel and SA312 TP316 stainless steel piping materials were used for the tests. The fracture resistance under a reversible cyclic load was considerably lower than that under monotonic load regardless of test temperature, material, and loading rate. Under both cyclic and monotonic loading conditions, the fracture behavior of SA312 TP316 stainless steel was independent of the loading rate at both room temperature and $316^{\circ}C$. For SA508 Gr.1a lowalloy steel, the loading rate effect on the fracture behavior was appreciable at $316^{\circ}C$ under cyclic and monotonic loading conditions. However, the loading rate effect diminished when the cyclic load ratio of the load (R) was -1. Thus, it was recognized that the fracture behavior of piping materials, including seismic loading characteristics, can be evaluated when tested under a cyclic load of R = -1 at a quasistatic loading rate.

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References

  1. ASME, ASME B&PV Code Sec. III, Nuclear Components, 1998.
  2. ASME, ASME B&PV Code Sec. XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1998.
  3. J.D. Stevenson, Summary of the historical development of seismic design of nuclear power plants in Japan and the U.S. Nucl. Eng. Des 269 (2014) 160-164. https://doi.org/10.1016/j.nucengdes.2013.08.023
  4. G. Saji, Safety goals for seismic and tsunami risks: lessons learned from the Fukushima Daiichi disaster, Nucl. Eng. Des 280 (2014) 449-463. https://doi.org/10.1016/j.nucengdes.2014.09.013
  5. USNRC, Evaluation of Potential Pipe Break, NUREG-1061 Vol. 3, 1984.
  6. USNRC, The Effect of Cyclic and Dynamic Loading on the Fracture Resistance of Nuclear Piping Steels, NUREG/CR-6440, 1996.
  7. C.S. Seok, K.L. Murty, A study on the decrease of fracture resistance curve under reversed cyclic loading, Int. J. Pres. Ves. Piping 77 (2000) 303-311. https://doi.org/10.1016/S0308-0161(00)00018-1
  8. P.K. Singh, V.R. Ranganath, S. Tarafder, P. Prasad, V. Bhasin, K.K. Vaze, H.S. Kushwaha, Effect of cyclic loading on elastic-plastic fracture resistance of PHT system piping material of PHWR, Int. J. Pres. Ves. Piping 80 (2003) 745-752. https://doi.org/10.1016/S0308-0161(03)00133-9
  9. B. Tranchand, S. Chapuliot, V. Aubin, S. Marie, M. Bourgeois, Ductile Fracture Analysis Under Large Amplitude Cycles, Proc. ASME PVP Conf. PVP2014-PVP28426, 2014.
  10. T. Chowdhury, S. Sivaprasad, H.N. Bar, S. Tarafder, N.R. Bandyopadhyay, Cyclic fracture behaviour of 20MnMoNi55 steel at room and elevated temperatures, Fat. Frac. Eng. Mater. Struc 38 (2015) 813-827. https://doi.org/10.1111/ffe.12267
  11. H. Roy, S. Sivaprasad, S. Tarafder, K.K. Ray, Monotonic vis-a-vis cyclic fracture behavior of ANSI 304LN stainless steel, Eng. Frac. Mech 76 (2009) 1822-1832. https://doi.org/10.1016/j.engfracmech.2009.04.001
  12. S.K. Gupta, V. Bhasin, J. Chattopadhyay, A.K. Ghosh, R.K. Singh, Cyclic-tearing behavior and JeR curves of Indian NPP pipes under displacement-controlled cyclic loading, Int. J. Pres. Ves. Piping 132-133 (2015) 72-86. https://doi.org/10.1016/j.ijpvp.2015.06.002
  13. ASTM, Standard Test Method for Measurement of Fracture Toughness, ASTM E1820-09, 2009.
  14. USNRC, Development of Technical Basis for Leak-Before-Break Procedure, NUREG/CR-6765, 2002.
  15. H.H. Johnson, Calibrating the electric potential method for studying slow crack growth, Mater. Res. Stand 5 (1965) 442-445.
  16. J.A. Joyce, G.E. Sutton, An automated method of computercontrolled low-cycle fatigue crack growth testing using the elasticeplastic parameter cyclic J, ASTM STP 877 (1985) 227-247.
  17. J.A. Joyce, E.M. Hackett, C. Roe, Effect of cyclic loading on the deformation and elastic-plastic fracture behaviour of cast stainless steel, ASTM STP 1207 (1994) 722-741.
  18. J.W. Kim, M.R. Choi, Effect of loading rate on the deformation behavior of SA508 Gr. 1a low-alloy steel and TP316 stainless steel pipe materials at RT and $316^{\circ}C$, Trans. KSME (A) 39 (2015) 383-390.
  19. USNRC, Effect of Dynamic Strain Aging on the Strength and Toughness of Nuclear Ferritic Piping at LWR Temperatures, NUREG/CR-6226, 1994.
  20. J.W. Kim, I.S. Kim, Investigation of dynamic strain aging on SA106 Gr. C piping steel, Nucl. Eng. Des 172 (1997) 49-59. https://doi.org/10.1016/S0029-5493(97)00045-9
  21. J.H. Yoon, B.S. Lee, Y.J. Oh, J.H. Hong, Effects of loading rate and temperature on JeR fracture resistance of an SA516eGr.70 steel for nuclear piping, Int. J. Pres. Ves. Piping 76 (1999) 663-670. https://doi.org/10.1016/S0308-0161(99)00033-2

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