화학공학소재연구정보센터
Journal of the Korean Industrial and Engineering Chemistry, Vol.9, No.5, 674-679, October, 1998
소듐 분위기에서 물누출에 의한 5Cr-1Mo Ferrite강 구멍의 막힘과 재개방 현상
Plugging and Re-opening Phenomena of the 5Cr-1Mo Steel Leak Hole by Water Leakage in Sodium Atmosphere
초록
액체금속로 증기발생기 전열관 재질로 사용이 예상되는 ferrite steel 시편을 사용해서 소듐분위기에서 미량의 물 누출 실험을 수행하였다. 누출경로는 소듐-물 반응생성물 및 부식생성물에 의한 self-plugging 현상과 열적인 transient 및 전열관의 vibration에 의한 re-opening 메카니즘으로 설명이 가능하였다. 실험결과, 600 Psig의 injection 압력으로 5g H2O를 소듐분위기 속의 시편으로 누출시킨 경우, 누출초기와 약 70분 경과 후에 약간의 누출 흔적이 보였으나, self-plugging되었던 누출경로는 129분이 경과되자 완전 re-opening된 것으로 확인되었다. 누출시편의 re-opening shape은 2중으로 되어 있었으며, 소듐부위에서 시편 표면에 나타난 re-opening size 약 2mm의 직경을 나타내었다.
Small water leak experiment was carried out in liquid sodium atmosphere using a specimen of ferrite steel, which will be expected to be a material of the heat transfer tube of liquid metal fast breeder reactor. Self-plugging phenomena of leak path could be explained by the products of reaction and corrosion by sodium-water reaction. Also, re-opening mechanism of self-plugged path could be explained by the thermal transient and vibration of heat transfer tube. As a result, perfect re-opening time of self-plugged leak path was observed to be 129 minutes after water leak initiation. Re-opening shape of a specimen was appeared with double layer of circular type, and re-opening size of this specimen surface was about 2 mm diameter on sodium side.
  1. Foust DJ, Sodium-NaK Engineering Handbook, Sodium Chemistry and Physical Properties, Gordon & Breach Science, New York (1972)
  2. Fromm W, WASH-1101, LMFBR Program Plan (OverallPlan), Element 1, U.S. Atomic Energy Commission (1973)
  3. Addison CC, The Chemistry of the Liquid Alkali Metals, John Wiley & Sons, New York (1984)
  4. Kanegae N, Hashiguchi K, Ikemoto I, Hori M, Trans. Am. Nucl. Soc., 24, 386 (1978)
  5. Nei H, "Wastage of Steam Generator Tubes During Small Leak of Steam into Sodium," ANS Topical Meeting on Fast Reactor Safety in Los Angeles, Califonia (1974)
  6. Bray JA, J. Brit. Nucl. Energy Soc., 10, 107 (1970)
  7. Budney GS, "Liquid Metal Heated Steam Generator Operating Experience," NAA-SR-12534 (1967)
  8. Cowen HC, Thorley AW, ND-R-984(R), "Caustic Cracking of 2 1/4Cr Mo Steel," United Kingdom Atomic Energy Authority, Nothern Division Report (1983)
  9. Spalaris CN, Challenger KD, Day RD, "Materials Engineering Issues, LMFBR Steam Generators," Int. Conf. on Liquid Metal Tech. in Energy Production, Held in Seven Springs (1976)
  10. Roy P, Spalaris CN, Nucl. Tech., 55, 259 (1981)
  11. Hori M, Kawashima K, Sato M, "Safety Evaluation of the Monju Steam Generator," Int. Meeting on Fast Reactor Safety Related Physics, Chicago, 709-718 (1976)
  12. Chamberlain HV, Cameron JA, APDA-254, "Studies of Material Wastage Resulting from Reactions of Water in Sodium,"
  13. Dumm K, "Sodium-Water Reaction: Effects of Small Waterside Leaks on the Sodium-Conducting Part of a Steam Generator (Orienting Preliminary Tests)," Interatom No. TM-130 (1965)
  14. Bridgman PW, The Physics of High Pressure, G. Bell & Sons, Ltd., London (1931)
  15. Sandusky DW, Trans. Am. Nucl. Soc., 19 (1974)
  16. Dumm K, Mausbeck H, Schnitker W, ATKE, 14, 309 (1969)
  17. Greene DA, "Small Leak Damage and Protection Systems in Steam Generators," Int. Conf. on Liquid Metal Tech. in Energy Production, Held in Seven Springs (1976)
  18. Sandusky DW, "Small Leak Shut-Down, Location and Behavior in LMFBR Steam Generator," Int. Conf. on Liquid Metal Tech. in Energy Production, Held in Seven Springs, 193-201 (1976)
  19. Hori M, Aomic Energy Rev., 18, 707 (1980)
  20. Greene DA, "Liquid Metal Engineering and Technology," Proceedings of the 3'rd International Conference, Held in Oxford, Paper No.-3 (1984)