Plugging and Re-opening Phenomena of the 5Cr-1Mo Steel Leak Hole by Water Leakage in Sodium Atmosphere

소듐 분위기에서 물누출에 의한 5Cr-1Mo Ferrite강 구멍의 막힘과 재개방 현상

  • Jeong, Kyung-Chai (Korea Atomic Energy Research Institute, KALIMER Verification Test Lab.) ;
  • Kim, Tae-Joon (Korea Atomic Energy Research Institute, KALIMER Verification Test Lab.) ;
  • Choi, Jong-Hyeun (Korea Atomic Energy Research Institute, KALIMER Verification Test Lab.) ;
  • Park, Jin-Ho (Korea Atomic Energy Research Institute, KALIMER Verification Test Lab.) ;
  • Hwang, Sung-Tai (Korea Atomic Energy Research Institute, KALIMER Verification Test Lab.)
  • 정경채 (한국원자력연구소 KALIMER검증 시험 Lab.) ;
  • 김태준 (한국원자력연구소 KALIMER검증 시험 Lab.) ;
  • 최종현 (한국원자력연구소 KALIMER검증 시험 Lab.) ;
  • 박진호 (한국원자력연구소 KALIMER검증 시험 Lab.) ;
  • 황성태 (한국원자력연구소 KALIMER검증 시험 Lab.)
  • Received : 1998.03.14
  • Accepted : 1998.06.16
  • Published : 1998.10.10

Abstract

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.

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 5 g $H_2O$를 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 2 mm의 직경을 나타내었다.

Keywords

Acknowledgement

Grant : 원자력개발 중장기 과제

Supported by : 과기부

References

  1. Sodium Chemistry and Physical Properties Sodium-Nak Engineering Handbook D. J. Foust
  2. WASH-101, LMFBR Program Plan (Overall Plan) W. Formm
  3. The Chemistry of the Liquid Alkali Metals C. C. Addison
  4. Trans. Am. Nucl. Soc. v.24 K. Nanegae;K. Hashiguchi;I. Ikemoto;M. Hori
  5. ANS Topical Meeting on Fast Reactor Safety in Los Angeles Wastage of Steam generator tubes during small leak of steam into sodium H. Nei
  6. NAA-SR-12534 Liquid metal heated stema generator operating experience G. S. Budney
  7. J. Brit. Nucl. Energy Soc. v.10 J. A. Bray
  8. United Kingdom Atomic Energy Authority, Northern Division Report Caustic cracking of 2 1/1Cr Mo steel H. C. Cowen;A. W. Thorley
  9. Int. Conf. on Liquid Metal Tech. Energy Production Materials engineering issues, LMFBR steam generators C. N. Spalaris;K. D. Challenger;R. A. Day
  10. Nucl. Tech. v.55 Some aspects of materials development for sodium heated steam generators P. Roy;C. N. Spalaris
  11. 動燃技報 No. 56 高速增殖爐用 蒸氣發生器の安全性試驗硏究の現況と今後の展開 田戀裕美
  12. Int. Meeting on Fast Reactor Safety Related Physics Safety evaluation of the Monju steam generator M. Hori;K. Kawashima;M. Sato
  13. APDA-254 Studies of material wastage resulting from reactions of water in sodium H. V. Chamberlain;J. A. Cameron(etc.)
  14. Interaton No. TM-130 Sodium-water reaction: effects of small water-side leaks on the sodium-conducting part of a steam generator(Orienting Preliminary Tests) K. Dumm
  15. The Physics of High Pressure P. W. Bridgman
  16. 日本原子力學會誌 v.25 高速爐用 蒸氣發生器 開發の現況 土屋每雄
  17. Trans. Am. Nucl. Soc. v.19 Behavior of small leaks in LMFBR steam generator D. W. Sandusky
  18. ATKE v.14 The reaction of sodium and water in tubes K. Kumm;H. Mausbeck;W. Schnitker
  19. Int. Conf. on Liquid Metal Tech. Energy Production Small leak damage and protection systems in steam generators D. A. Greene
  20. Int. Conf. on Liquid Metal Tech. Energy Production Small leak damage and protection systems in steam generators D. W. Sandusky
  21. Aomic Energy Review v.18 Sodium/water reactions in steam generators of liquid metal fast breeder reactors M. Hori
  22. Proceedins of the 3rd International Conference, Paper No. -3 Liquid metal engineering and technology D. A. Greene