DOI QR코드

DOI QR Code

저주기 피로부하에서 F82H 강 TIG 용접 접합부의 피로손상거동

Fatigue Damage Behavior in TIG Welded Joint of F82H Steel under Low Cycle Fatigue Loading

  • 김동현 (영산대학교 기계설계학과) ;
  • 박기원 (영산대학교 그린자동차학과)
  • Kim, Dong-Hyun (Dept. of Mechanical Design Engineering, Youngsan University) ;
  • Park, Ki-Won (Dept. of Green Automobile Engineering, Youngsan University)
  • 투고 : 2015.10.23
  • 심사 : 2015.12.10
  • 발행 : 2015.12.30

초록

Reduced activation ferritic/martensitic steels are recognized as the primary candidate structural materials for fusion blanket systems. Welding is an inevitable for breeding blanket for pressure tightness and radioisotope confinement. Especially, TIG welding was chosen for sealing because it has the largest gap allowance compared to the other welding methods, and its properties are controllable by feed wire and welding conditions. In this study, the low cycle fatigue test using two-type gage such as extensometer and strain gage was applied to the TIG welded joint of F82H steel, for evaluating fatigue damage accumulation behavior of the HAZs. As the result, the over-tempered HAZ have shown a higher fatigue damage accumulation compared with other materials at all the testing conditions.

키워드

참고문헌

  1. International energy agency (IEA) , World energy outlook 2011, http://www.iae.org
  2. A. Kohyama , Present status of low activation materials R&D for fusion, Journal of Plasma and Fusion Research, 79-9 (1999), 1018-1028
  3. A. Kohyama, A. Hishinuma, D.S. Gelles, R.L. Klueh, W. Dietz and K. Ehrlich, Low-activation ferritic and martensitic steels for fusion application, Journal of Nuclear Materials, 233-237 (1996), 138-147 https://doi.org/10.1016/S0022-3115(96)00327-3
  4. A. Hishinuma, A. Kohyama, R.L. Klueh, D.S. Gelles, W. Dietz and K. Ehrlich , Current status and future R&D for reduced-activation ferritic/martensitic steels, Journal of nuclear materials, 258-263 (1998), 193-204 https://doi.org/10.1016/S0022-3115(98)00395-X
  5. H. Tanigawa, T. Hirose, K. Shiba, R. Kasada, E. Wakai, H. Serizawa, Y. Kawahito, S. Jitsukawa, A. Kimura, Y. Kohno, A. Kohyama, S. Katayama, H. Mori, K. Nishimoto, R.L. Klueh, M.A. Sokolov, R.E. Stoller and S.J. Zinkle , Technical issues of reduced activation ferritic/ martensitic steels for fabrication of ITER test blanket modules, Fusion Engineering and Design, 83 (2008), 1471-1476 https://doi.org/10.1016/j.fusengdes.2008.07.024
  6. H. Tanigawa, K. Shiba, A. Möslang, R.E. Stoller, R. Lindau, M.A. Sokolov, G.R. Odette, R.J. Kurtz and S. Jitsukawa , Status and key issues of reduced activation ferritic/martensitic steels as the structural for a DEMO blanket, Journal of Nuclear Materials, 417 (2011), 9-15 https://doi.org/10.1016/j.jnucmat.2011.05.023
  7. Han-Ki Yoon, Sang-Pil Lee, Dong-Hyun Kim and Akira Kohyama , Strength characteristics of reduced activation ferritic steel for fusion blanket by TIG welding, Journal of KWJS, 21-1 (2003), 87-92 (in Korean)
  8. Sung-Yong Ahn and Namhyun Kang , The effects of $\delta$-ferrite on weldment of 9-12% Cr steels, Journal of KWJS, 31-6 (2013), 8-16 (in Korean)
  9. Joonoh Moon, Chang-Hoon Lee and Tae-Ho Lee , Microstructure and impact properties in the weld heat affected zone of a reduced activation ferritic/martensitic steel, Abstract of KWJS, 60 (2014), 16 (in Korean)
  10. T. Sawai, K. Shiba and A. Hishinuma , Microstructure of welded and thermal-aged low activation steel F82H IEA heat, Journal of nuclear materials, 283-287 (2000), 657-661 https://doi.org/10.1016/S0022-3115(00)00089-1
  11. T. Hirose, H. Sakasegawa, M. Nakajima and H. Tanigawa, Mechanical properties of TIG and EB weld joints of F82H, Fusion Engineering and Design, (2015), In press
  12. American Society for Testing and Materials , Standard Practice for Strain-Controlled Fatigue Testing, ASTM E606-92 (1992), 11-12
  13. K.T. Rie and H.P. Stuwe , A note on the influence of dwell time on low-cycle fatigue, International Journal of Fracture, 10-4 (1974), 545- 548 https://doi.org/10.1007/BF00155257
  14. O.K. Chopra and G.L. Stevens, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, Argon National Laboratory, NUREG/CR-6909 (2014), 1-176