Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Bi-linear Stress-Strain Curves for Considering Cyclic Hardening Behavior of Materials in the Nonlinear FE Analysis under Seismic Loading Conditions

지진하중 조건의 비선형 유한요소해석에서 반복경화 거동 고려를 위한 Bi-linear 응력-변형률 곡선

  • 정현준 (조선대학교 원자력공학과) ;
  • 김진원 (조선대학교 원자력공학과) ;
  • 김종성 (세종대학교 원자력공학과) ;
  • 구경회 (한국원자력연구원)
  • Received : 2018.11.09
  • Accepted : 2018.12.04
  • Published : 2018.12.30
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Abstract

This study compares true stress-true strain curves obtained by tensile tests of various piping materials with bi-linear stress-strain approximation suggested in the JSME Code Case(CC) Draft, a guideline for piping seismic inelastic response analysis. Based on the comparisons, the reliability of the bi-linear approximation is evaluated. It is found that bi-linear stress-strain curve of TP316 stainless steel is in good agreement with its true stress-true strain curve. However, Bi-linear stress-strain curves of TP304 stainless steel and carbon steels determined by the approximation cannot appropriately estimate their stress-strain behavior. Accordingly new bi-linear approximations for carbon steels and low-alloy steels are proposed. The proposed bi-linear approximations for carbon and low-alloy steels, which include the temperature effect on strength and hardening of material, estimate their stress-strain behavior reasonably well.

Keywords

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Fig. 1 Schematic diagram for determining Bi-linear stress-strain approximation from true stress-true strain curve

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Fig. 2 Comparison of Bi-linear stress-strain curves of SA312 TP316 and TP304 stainless steels determined by JSME CC and their true stress-strain curves

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Fig. 3 Comparison of Bi-linear stress-strain curves determined by using Cy and CE of TP316 and TP304 stainless steels and true stress-strain curves of SA312 TP347 and CF8A cast austenitic stainless steels

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Fig. 4 Comparison of Bi-linear stress-strain curves of carbon steels determined by JSME CC and true stress-strain curves of SA106 Gr.B and Gr.C carbon steels

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Fig. 5 Comparison of Bi-linear stress-strain curves of carbon steel determined by JSME CC and true stress-strain curves of SA508 Gr.1a low-alloy steel

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Fig. 6 Proposed new Cy and CE for carbon steel piping material

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Fig. 7 Proposed new Cy and CE for low-alloy steel piping material

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Fig. 8 Comparison of Bi-linear stress-strain curves determined by proposed model and true stress-strain curves

Table 1 Comparison of Cy and CE of austenitic stainless steels given by JSME CC and those obtained from experimental data

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Table 2 Comparison of Cy and CE for carbon steels given by JSME CC and those obtained from the experimental data

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References

  1. Saji, G., 2014, "Safety goals for seismic and tsunami risks: Lessons learned from the Fukushima Daiichi disaster," Nucl. Eng. Des., Vol.280, pp.449-463. https://doi.org/10.1016/j.nucengdes.2014.09.013
  2. Stevenson, J.D., 2014, "Summary of the historical development of seismic design of nuclear power plants in Japan and the U.S.," Nucl. Eng. Des., Vol.269, pp.160-164. https://doi.org/10.1016/j.nucengdes.2013.08.023
  3. IAEA, 2016, "Consideration of the application of the IAEA safety requirements for the design of nuclear power plants," International Atomic Energy Agency, Vienna, IAEA TECDOC-1791.
  4. ASME BPVC Sec. III Div.1 Sub. NB, 2007, "Rules for Construction of Nuclear Facility Components," American Society of Mechanical Engineers, NY.
  5. Donavin, P.R., 2016, "Technical Basis for Proposed ASME Section XI Code Case on Beyond Design Bases Earthquake," Proc. of ASME 2016 PVP Conference, Vancouver, BC, July 17-21, PVP2016-63827.
  6. Nakamura, I. and Kasahara, N., 2015, "Excitation tests on elbow pipe specimens to investigate failure behavior under excessive seismic loads," Proc. of ASME 2015 PVP Conference, Boston, MA, July 19-23, PVP2015-45711.
  7. OECD/NEA, 2015, "Interim Report on Metallic Components Margins under High Seismic Loads," Nuclear Energy Agency, Paris, NEA/CSNI/R(2015)8.
  8. Paul, S. K. Sivaprasad, S., Dhar, S., and Tarafder, S., 2011, "Key issues in cyclic plastic deformation: Experimentation," Mech. of Mater., Vol.43, pp.705-720. https://doi.org/10.1016/j.mechmat.2011.07.011
  9. Jeon, D. S., Kang, J. Y., Huh, N. S., Kim, J. S., and Kim, Y. J., 2017, "Effects of Hardening Models on Cyclic Deformation Behavior of Tensile Specimen and Nuclear Piping System," Trans. of the KPVP, Vol.13, No.2, pp.67-74.
  10. Chaboche, J. L., Dnag Van, K., and Gordier, G., 1979, "Modelization of the Strain Memory Effect on the Cyclic Hardening of 316 Stainless Steel," Proc. of 5th Int. Conference on SMiRT, Div.L, Berlin, Germany.
  11. Otani, A., Shibutani, T., Morishita, M, Nakamura, I., Watanabe, T., and Shiratori, M., 2017, "Seismic Qualification of Piping System by Detailed Inelastic Response Analysis Part 2. A Guideline for Piping Seismic Inelastic Response Anslysis," Proc. of ASME 2017 PVP Conference, Wailkoloa, HW, July 16-20, PVP2017-65190.
  12. ASME BPVC Sec. II Part D, 2010, "Properties Materials," American Society of Mechanical Engineers, NY.
  13. Morishita, M, Otani, A., Watanabe, T., Nakamura, I., Shibutani, T., and Shiratori, M., 2017, "Seismic Qualification of Piping System by Detailed Inelastic Response Analysis Part 1. A Code Case for Piping Sesimic Evaluation Based on Detailed Inelastic Response Analysis," Proc. of ASME 2017 PVP Conference, Wailkoloa, HW, July 16-20, PVP2017-65166.
  14. Nara, K., Nakamura, K., Yasunami, H., Kawabata, F., and Shiwaku, T., 2004, "Statistic investigation for thickness and strength of structural steel plate used for bridge," J. of Jap. Soc. Civ. Eng., No.752/I-66, pp.299-310 (in Japanese).
  15. JSME, 2015, "Code for nuclear power generation facilities: rules on design and construction for nuclear power plants", Japanese Society of Mechanical Engineers, JSME SNC1-2015(in Japanese).
  16. Nakamura, I., Otani, A., Morishita, M, Shiratori, M., Watanabe, T., and Shibutani, T., 2017, "Seismic Qualification of Piping System by Detailed Inelastic Response Analysis Part 3 - Variation in Elastic-Plastic Analysis Results on Carbon Steel Pipes from the Benchmark Analyses and the Parametric Analysis," Proc. of ASME 2017 PVP Conference, Wailkoloa, HW, July 16-20, PVP2017-65316.