DOI QR코드

DOI QR Code

Microstructure characterization technique of spacer garter spring coil X-750 material

스페이서 가터 스프링 코일 X-750 소재 정밀 조직 분석 방법

  • 진형하 (한국원자력연구원 (재료안전기술연구부)) ;
  • 류이슬 (한국원자력연구원 (재료안전기술연구부)) ;
  • 이경근 (한국원자력연구원 (재료안전기술연구부))
  • Received : 2021.11.11
  • Accepted : 2021.12.16
  • Published : 2021.12.31

Abstract

In the periodic surveillance material test for the spacer component of fuel channel assembly in CANDU, a microstructural characterization analysis is required in addition to the mechanical property evaluation test. In this study, detailed microstructure analysis and simple mechanical property evaluation of archive spacer parts were conducted to indirectly support the surveillance test and assist in the study of spacer material degradation. We investigated the microstructural characteristics of the spacer garter spring coil through comparative analysis with the plate material. The main microstructure characteristics of the garter spring coil X-750 are represented by the fine grain size distribution, the ordering phase distribution developed inside the matrix, the high dislocation density inside the grains, and the arrangement of coarse carbides. In addition, the yield strength of the garter spring coil X-750 was indirectly evaluated to be approximately 1 GPa. We also established an analytical method to elucidate the microstructural evolution of the radioactive spacer garter spring coil X-750 based on Canadian research experiences. Finally, we confirmed the measurement technique for helium bubble formation through TEM examination on the helium implanted X-750 material.

Keywords

Acknowledgement

This work was supported by the Ministry of Science and ICT and the National Research Foundation of Korea (NRF) grant funded by the Korea government (2017M2A8A4015157)

References

  1. M. Griffiths, 2013, "The Effect of Irradiation on Ni-containing Components in CANDU® Reactor Cores: A Review," CNL Nuclear Review, Vol 2, pp. 1-16. doi:https://doi.org/10.12943/ANR.2013.00001.
  2. M. Griffiths, G.A. Bickel, S.A. Donohue, P. Feenstra, C.D. Judge, D. Poff, L. Walters, M.D. Wright, L. Greenwood and F.A. Garner, 2013, "Degradation of Ni-alloy components in CANDU reactor cores," AECL-CW-127000-CONF-007.
  3. C.D Judge, M. Griffiths, L Walters, M Wright, G A. Botton, O.T. Woo, M Stewart, S.R. Douglas, F.A. Garner, 2012, "Embrittlement of Nickel Alloys in a CANDU Reactor Environment" Effect of Radiation on Nuclear Materials: 25th, Vol. STP 1547, pp 161-175.
  4. CSA N 285.4-14, 2014, "Periodic inspection of CANDU nuclear power plant components," CSA Group, Ontario, CANADA.
  5. H K Zhang, F. Long, M.R. Daymond, 2013, "Novel techniques of preparing TEM samples for characterization of irradiation damage," J. Microsc., Vol 252(3), pp 251-257. doi:https://doi.org/10.1111/jmi.12085.
  6. "INCONEL® Alloy X-750", Special Metals Corporation, SMC-067, 2004, Available at: https://www.specialmetals.com/documents/technical-bulletins/inconel/inconel-alloy-x-750.pdf.
  7. H W Ha, B S Seong, H W Jeong, Y S Choi, N Kang, 2015, "Effects of the aging temperature and stress relaxation conditions on precipitation in Inconel X-750", J. Nucl. Mater., Vol 457, pp 362-368. doi:https://doi.org/10.1016/j.jnucmat.2014.11.093.
  8. C. Howard, C.D. Judge, D. Poff, S parker, M. Griffiths, P. Hosemann, 2018, "A novel in-situ, lift-out, three-point bend technique to quantify the mechanical properties of an ex-service neutron irradiated inconel X-750 component," J. Nucl. Mater., Vol 498, pp 149-158.doi:https://doi.org/10.1016/j.jnucmat.2017.10.002.
  9. J T Busby, M C. Hash, G S. Was, 2005, "The relationship between hardness and yield stress in irradiated austenitic and ferritic steels," J. Nucl. Mater., Vol 336(2-3), pp 267-278. doi:https://doi.org/10.1016/j.jnucmat.2004.09.024.
  10. H. Dunn, G A. Bickel, 2018, "Hotcell Examinations of In-core Inconel X-750 spacers removed from CANDU Reactors for Surveillance," 55th annual metting on Hot Laboratories and Remote Handling - HOTLAB, Helsinki, Finland.
  11. C. Howard, C. Judge, V Bhakhri, M Mattucci, H. Rajakumar, C Mayhew, C. Dixon, D. Pof, G. Bickel, J. Wang, D. Murray, F. Teng, 2019, "Advanced Multi-Scale Post-Irradiation Experiments Link the Mechanical Properties and Deformation Mechanisms of In Core lnconel X-750 Spacers," 56th annual metting on Hot Laboratories and Remote Handling - HOTLAB, Mamallapuram, India.
  12. J. Kwon, H-H. Jin, G-G. Lee. D-H. Park, 2019, " Radiation damage to Ni-Based alloys in Wolsong CANDU ractor environment," Nucl. Eng. Technol, 51(3), pp 915-921. doi:https://doi.org/10.1016/j.net.2018.11.015.
  13. T. Malis, S.C. Cheng, R.F. Egerton, 1988, "EELS log ratio technique for specimen-thickness measurement in the TEM," J. Electron Microsc. Tech., Vol 8(2), pp 193-200. doi:https://doi.org/10.1002/jemt.1060080206.