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Simulating Nuetron Irradiation Effect on Cyclic Deformation and Failure Behaviors using Cold-worked TP304 Stainless Steel Base and Weld Metals

냉간가공된 TP304 스테인리스강 모재와 용접재를 이용한 반복 변형 및 손상 거동에 미치는 중성자조사 영향 모사

  • 김상언 (조선대학교 원자력공학과) ;
  • 김진원 (조선대학교 원자력공학과)
  • Received : 2020.12.01
  • Accepted : 2020.12.10
  • Published : 2020.12.30

Abstract

This study presents cyclic stress-strain and tensile test results at room temperature (RT) and 316℃ using cold-worked TP304 stainless steel base and weld metals. By comparing the cyclic hardening/softening behavior and failure cycle of cold-worked materials with those of irradiated austenitic stainless steels, the feasibility of simulating the irradiation effect on cyclic deformation and failure behaviors of TP304 stainless steel base and weld metals was investigated. It was found that, in the absence of strain-induced martensite trasformation, cold-working could properly simulate the change in cyclic hardening/softening behavior of TP304 stainless steel base and weld metals due to neutron irradiation. It was also recognized that cold-working could adequately simulate the reduction in failure cycles of TP304 stainless steel base and weld metals due to neutron irradition in the low-cycle fatigue region.

Keywords

References

  1. Kim, J.S., 2015, "Structural Integrity Analysis of Lower Core Plate in Pressurized Water Reactors Considering Stress Triaxiality," Procedia Eng., Vol.130, pp.1494-1502. doi:https://doi.org/10.1016/j.proeng.2015.12.318
  2. EPRI, 2007, "Materials Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data-State of Knowledge (MRP-211)," Electric Power Research Institute, Palo Alto, CA, 1015013.
  3. Shah, V.N. and Macdonald, P.E., 1993, Aging and Life Extension of Major Light Water Reactor Components, Elsevier Science Pub., Amsterdam
  4. O.K. Chopra and A.S. Rao, 2011, "A review of irradiation effects on LWR core internal materials - Neutron embrittlement," J. Nucl. Mater., Vol.412, pp.195-208. doi:https://doi.org/10.1016/j.jnucmat.2011.02.059
  5. Kenik, E.A. and Busby, J.T., 2012, "Radiation-induced degradation of stainless steel light water reactor internals," Mater. Sci. Eng. R, Vol.73, pp.67-83. doi:https://doi.org/10.1016/j.mser.2012.05.002
  6. IAEA, 1999, "Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals," IAEA TECDOC-1119.
  7. IAEA, 2016, "Consideration of the application of the IAEA safety requirements for the design of nuclear power plants," IAEA TECDOC-1791.
  8. EPRI, 2013, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-term Task Force Recommendation 2.1: Seismic," Electric Power Research Institute, Palo Alto, CA, 3002000704.
  9. JSME, 2014, Lessons Learned from the Great East Japan Earthquake Disaster, http://www.jsme.or.jp/English
  10. Jitsukawa, S., Shiba, K., Hishinuma, A., and Alexander, D.J., 1996, "Comparison of elastic-plastic fracture toughness of irradiated and cold-worked JPCA using miniaturized DCT specimens," J. Nucl. Mater., Vol.233-237, pp.152-155. doi:https://doi.org/10.1016/ S0022-3115(96)00204-8
  11. Kamaya, M., 2015, "Elastic-plastic failure assessment of cold worked stainless steel pipes," Int. J. Pres. Ves. Pip., Vol.131, pp.45-51. doi:https://doi.org/10.1016/j. ijpvp.2015.04.008
  12. Ogawa, T., Ono, Y., Itatani, M., Hayashi, T., and Saito, T., 2020, "Evaluation of mechanical properties distribution for irradiated stainless steels simulated by utilizing the gradient of the cold working ratio," Int. J. Pres. Ves. Pip., Vol. 179, 103939. doi:https://doi.org/10.1016/j.ijpvp.2019.103939
  13. Kim, J.W. and Kim, Y.J., 2019, "Feasibility analysis of simulation on the mechanical properties of neutron irradiated austenitic stainless steels by cold-work," Trans. of KPVP, Vol. 15, No.2, pp.9-18. doi: https://doi.org/10.20466/KPVP.2019.15.2.009
  14. ASTM E606-92, 1998, Standard Practice for Strain-Controlled Fatigue Testing (Reapproved 1998), ASTM International, West Conshohocken, PA.
  15. ASTM E8/E8M-16, 2016, "Standard Test Method for Tension Testing of Metallic Materials," ASTM International, West Conshohocken, PA.
  16. Pawel, J.E., Rowcliffe, A.F., Lucas, G.E., and Zinkle, S.J., 1996, "Irradiation performance of stainless steels for ITER application," J. Nucl. Mater.. Vol.239, pp.126-131. doi:https://doi.org/10.1016/S0022-3115(96)00484-9
  17. ASM, "Fatigue and Fracture," ASM Handbook, Vol. 19, 1996.
  18. Paul, S.K., Sivaprasad, S., Dhar, S., and Tarafder, S., 2011, "Key issues in cyclic plastic deformation: Experimentation," Mech. Mater., Vol.41, pp.705-720. doi:https://doi.org/10.1016/j.mechmat.2011.07.011
  19. Kim, C., 2018, "Nondestructive evaluation of strain-induced phase transformation and damage accumulation in austenitic stainless steel subjected to cyclic loading," Metals, Vol.8, pp.1-14. doi: https://doi.org/10.3390/met8010014
  20. Facheris, G., 2014, Cyclic plastic material behavior leading to crack initiation in stainless steel under complex fatigue loading conditions, Mechanical Engineering, Politecnico di Milano, Ph.D thesis.
  21. Man, J., Smaga, M., Kubena, I., Eifler, D., and Polak, J., 2017, "Effect of metallurgical variables on the austenite stability in fatigued AISI 304 type steels," Eng. Fract. Mech., Vol. 185, pp.139-159. doi:https://doi.org/10.1016/j.engfracmech.2017.04.041
  22. Devries, M.I., Tjoa, G.L., and Elen, J.D., 1979, "Effects of neutron irradiation on low-cycle fatigue and tensile properties of AISI Type 304 stainless steel at 298K," Fatigue Fract. Eng. M., Vol.1, pp.159-171. doi:https://doi.org/10.1111/j.1460-2695.1979.tb00375.x
  23. Puzzolante, J.L., Scibetta, M., Chaouadi, R., and Vandermeulen, W., 2000, "Tensile and low-cycle fatigue properties of solution annealed type 316L stainless steel plate and TIG-weld exposed to 5 dpa at low-temperature (42℃)" J. Nucl. Mater., Vol. 283-287, pp.428-434. doi:https://doi.org/10.1016/S0022-3115(00)00367-6
  24. Murty, K.L. and Charit, I., 2012, Introduction to Nuclear Materials - Fundamentals and Applications, Wiley-VCH.