Nuclear Engineering and Technology

  • 제41권1호
  • /
  • Pages.107-112
  • /
  • 2009
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

CORROSION BEHAVIOR OF NI-BASE ALLOYS IN SUPERCRITICAL WATER

  • Zhang, Qiang (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Tang, Rui (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Li, Cong (China Nuclear Power Technology Research Institute) ;
  • Luo, Xin (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Long, Chongsheng (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Yin, Kaiju (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China)
  • 발행 : 2009.02.28
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Corrosion of nickel-base alloys (Hastelloy C-276, Inconel 625, and Inconel X-750) in $500^{\circ}C$, 25MPa supercritical water (with 10 wppb oxygen) was investigated to evaluate the suitability of these alloys for use in supercritical water reactors. Oxide scales formed on the samples were characterized by gravimetry, scanning electron microscopy/energy dispersive spectroscopy, X-ray diffraction, and X-ray photoelectron spectroscopy. The results indicate that, during the 1000h exposure, a dense spinel oxide layer, mainly consisting of a fine Cr-rich inner layer ($NiCr_{2}O_{4}$) underneath a coarse Fe-rich outer layer ($NiFe_{2}O_{4}$), developed on each alloy. Besides general corrosion, nodular corrosion occurred on alloy 625 possibly resulting from local attack of ${\gamma}$" clusters in the matrix. The mass gains for all alloys were small, while alloy X -750 exhibited the highest oxidation rate, probably due to the absence of Mo.

키워드

참고문헌

  1. T.C. Totemeier, D.E. Clark. Effect of transient thermal cycles in a supercritical water-cooled reactor on the microstructure and properties of ferritic-martensitic steels. Journal of Nuclear Materials, 2006, 355: 104 https://doi.org/10.1016/j.jnucmat.2006.04.007
  2. D.R. Novog, J. Luxat, L.K.H. Leung. Estimation of conceptual supercritical water reactor response to a small loss of coolant accident. 3rd Int. symposium on SCWRDesign and Technology, 2007: 108-117
  3. Y. Chen, K. Sridharan, T. Allen. Corrosion behavior of ferritic-martensitic steel T91 in supercritical water. Corrosion Science, 2006, 48 (9): 2843-2854 https://doi.org/10.1016/j.corsci.2005.08.021
  4. L. Tan, Y. Yang, T. R. Allen. Oxidation behavior of ironbased alloy HCM12A exposed in supercritical water. Corrosion Science, 2006, 48 (10): 3123-2138 https://doi.org/10.1016/j.corsci.2005.10.010
  5. Yongsun Yi, Byeonghak Lee, Sungho Kim, et al. Corrosion and corrosion fatigue behaviors of 9cr steel in a supercritical water condition. Materials Science and Engineering A, 2006, 429: 161–168 https://doi.org/10.1016/j.msea.2006.05.035
  6. X. Gao, X. Wu, Z. Zhang, et al. Characterization of oxide films grown on 316L stainless steel exposed to H2O2- containing supercritical water. Journal of Supercritical Fluids, 2007, 42: 157-163 https://doi.org/10.1016/j.supflu.2006.12.020
  7. X. Luo, R. Tang, C.S. Long, et al. Corrosion behavior of austenitic and ferritic steels in supercritical water. Nucl. Eng. Technol., 2008, 40 (2):147-154 https://doi.org/10.5516/NET.2008.40.2.147
  8. X. Ren, K. Sridharan, T.R. Allen. Corrosion of ferriticmartensitic steel HT9 in supercritical water. Journal of Nuclear Materials, 2006, 358: 227-234 https://doi.org/10.1016/j.jnucmat.2006.07.010
  9. L. Tan, M.T. Machut, K. Sridharan, et al. Corrosion behavior of a ferritic/ martensitic steel HCM12A exposed to harsh environments. Journal of Nuclear Materials, 2007, 371: 161-170 https://doi.org/10.1016/j.jnucmat.2007.05.001
  10. Pantip Ampornrat, Gary S. Was Oxidation of ferriticmartensitic alloys T91, HCM12A and HT-9 in supercritical water. Journal of Nuclear Materials, 2007, 371: 1-17 https://doi.org/10.1016/j.jnucmat.2007.05.023
  11. B.P. Somerday, K.T. Wiggans, R.W. Bradshaw. Environmentassisted failure of alloy C-276 burst disks in a batch supercritical water oxidation reactor. Engineering Failure Analysis, 2006, 13: 80-95 https://doi.org/10.1016/j.engfailanal.2004.10.017
  12. S.E. Ziemniak, M. Hanson. Corrosion behavior of NiCrMo Alloy 625 in high temperature, hydrogenated water. Corrosion Science, 2003, 45: 1595-1618 https://doi.org/10.1016/S0010-938X(02)00230-5
  13. S.E. Ziemniak, M. Hanson. Corrosion behavior of NiCrFe Alloy 600 in high temperature, hydrogenated water. Corrosion Science, 2006, 48: 498-521 https://doi.org/10.1016/j.corsci.2005.01.006
  14. L. Tan, K. Sridharan, T. R. Allen. The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water. Journal of Nuclear Materials, 2006, 348: 263-271 https://doi.org/10.1016/j.jnucmat.2005.09.023
  15. G.S. Was, P. Ampornrat, G. Gupta, et al. Corrosion and stress corrosion cracking in supercritical water. Journal of Nuclear Materials, 2007, 371: 176-201 https://doi.org/10.1016/j.jnucmat.2007.05.017
  16. D. Rats, L. Vandenbulcke, R. Herbin, R. Benoit, R. Erre, V. Serin, J. Sevely, Thin Solid Films 270 (1995) 177
  17. G. Latha, N. Rajendran, S. Rajeswari, J. Mater. Eng. Perform. 6 (1997) 743 https://doi.org/10.1007/s11665-997-0076-2
  18. H.C. Brookes, J.W. Bayles, F.J. Graham, J. Appl. Electrochem. 20 (1990) 223 https://doi.org/10.1007/BF01033598

피인용 문헌

  1. Surface oxide formation on IN625 and plasma sprayed NiCrAlY after high density and low density supercritical water testing vol.65, pp.8, 2012, https://doi.org/10.1002/maco.201206613
  2. Alloy 800H under supercritical water conditions: a flow reactor study of corrosion and hydrogen evolution vol.66, pp.12, 2015, https://doi.org/10.1002/maco.201508315
  3. Multiscale model of metal alloy oxidation at grain boundaries vol.142, pp.21, 2015, https://doi.org/10.1063/1.4921940
  4. Corrosion Behavior of Alloy C-276 in Supercritical Water vol.2018, pp.1687-8442, 2018, https://doi.org/10.1155/2018/1027640