Applied Chemistry for Engineering (공업화학)

The Korean Society of Industrial and Engineering Chemistry (한국공업화학회)
권호 표지

Reaction Phenomena of the Ferrite Steel by Water Leakage into Liquid Sodium

소듐분위기에서 물 누출로 인한 Ferrite Steel에서의 반응현상

  • Received : 1997.12.11
  • Accepted : 1998.02.23
  • Published : 1998.04.10
Download PDF
⟨ Previous Next ⟩

Abstract

Water leak phenomena in the liquid sodium which is a coolant of liquid metal reactor, were investigated by carrying out sodium-water reaction experiment. It was confirmed that sodium and water react each other by the analysis of material composition of aspecimen at the end of experiment. When steam of $100kg/cm^2$ was passed through the leak path of the specimen for 4 hours, reaction products from sodium-water reaction were observed on the leak site. However, re-opening phenomena were not observed at this condition. It was interpretted that the reaction product precipitated on leak path and thermal transient caused self-plugging and re-openning phenomena, respectively.

액체금속로 냉각재인 액체 소듐에서 시편의 누출특성을 소듐-물 반응 실험에 의해 조사하였다. 소듐-물 반응 현상의 확인은 물 누출 실험 전후에 Fe, Cr 및 Ni 등과 같은 시편의 조성 변화로 확인하였다. $100kg/cm^2$의 누출 압력으로 4시간 동안 시편의 누출 경로를 통해 물을 누출시킨 결과, 누출경로에서 소듐-물 반응생성물들이 침적되어 있는 것을 확인하였으나, 부식에 의해 누출경로가 완전 파열되어 다량의 수증기가 액체 소듐속으로 빠져나가는 re-openning 현상은 관찰되지 않았다. 시편의 누출경로가 막히는 self-plugging 현상은 소듐-물 반응에 의한 반응생성물과 시편의 부식에 의한 부식 생성물이 주 원인으로 추정되고, re-openning 현상은 시편의 누출경로에서 열적인 transient로 추정되었다.

Keywords

References

  1. Progress in Nuclear Energy v.20 Fast reactor progress-Slow but Sure R. D. Smith
  2. Nucl. Energy v.25 Liquid metal fast breeder reactor steam generator design and experience in the U. K. J. K. Butler;O. Hayden
  3. Symp. Fast Breeder Reactors: Experience and Trends Main directions for decreasing the capital costs of LMFBRs J. H. Crowley;G. H. Pavlenco
  4. Sodium-Nak Engineering Handbook : Sodium chemistry and physical properties O. T. Foust
  5. Proceeding of the speciallists' meeting on SG failure and failure propagation experience, IWGFR-78 A Model of the propagation of water leaks into sodium in steam generator J. P. Maupre;K. B. McCrindle
  6. Int. Conf. on Liquid Metal Tech. in Energy Production Fail-safety of the EBR-Ⅱ steam generator systems P. S. Chopra;C. C. Stone(et al.)
  7. NRL Memo report-33 A study of the sodium-hydrogen-oxygen systems D. D. Williams
  8. APDA-254 Studies of material wastage resulting from reactions of water in sodium H. V. Chamberlain(et al.)
  9. IAEA study group meeting on steam generator for LMFBRs, Summary repot IWGFR-1 Sodium/water wastage and reaction program D. A. Greene
  10. Nucl. Tech. v.12 Characterization of diffusion tube hydrogen detector in dynamic sodium system P. Roy;D. N. Rodgers
  11. PNC report-N041 Analytical treatment of large leak pressure behavior in LMFBR steam generators M. Hori(et al.)
  12. Kerntechnik v.16 Studies on the safety engineering design of the steam generators of the SNR-300 K. Dumm;H. Mausbeck
  13. Int. Conf. Liquid Metal Technology Ⅰ. Energy Production Small leak damage and protection systems in steam generator D. A. Greene
  14. APDA-254 Studies of material wastage resulting from reaction of water in sodium H. V. Chamberlain;J. A. Cameron(et al.)
  15. Trans. Am. Nucl. Soc. v.19 Behavior of small leaks in LMFBR steam generators D. W. Sandusky
  16. The physics of high pressure P. W. Bridgman
  17. Proc. of 3'rd Int. Conf. Sodium-water reaction phenomena associated with small leaks in LMFBR steam generator D. A. Greene