Self-wastage에 의한 2.25Cr-1Mo Steel 시편의 Re-open 현상

정경채; 권상운; 최종현; 박진호; 황성태

Journal of the Korean Industrial and Engineering Chemistry, Vol.10, No.4, 531-536, June, 1999

Export Citation

Self-wastage에 의한 2.25Cr-1Mo Steel 시편의 Re-open 현상

Reopening Phenomena of the 2.25Cr-1Mo Steel Specimen by Self-wastage

정경채, 권상운, 최종현, 박진호, 황성태

초록

누출시험 장치를 이용하여 미량 물 누출 실험을 수행하였다. 2.25Cr-1Mo 시편의 누출경로는 나트륨-물 반응 생성물에 의해 plugging되는 경우가 발생하였으나, 대부분 re-open상태를 나타내었다. 또한 누출 경로가 완전 re-open된 후 나트륨 부위에서 시편의 self-wastage pattern은 온도에 영향을 받지 않음을 알 수 있었으며, 누출경로가 re-open 되면서 나타나는 defected 크기는 대략 5 mm 이내임을 알 수 있었다. 누출 경로가 완전 re-open 되는데 걸리는 시간은 나트륨 온도가 높을수록 짧게 나타났으며, 평균적으로 450 ℃에서 143분, 475 ℃ 의 경우 40.7분, 510 ℃의 경우 34.7분을 나타내었다.

Experiments on micro-leak of water were carried out with the water injecting simulator in liquid sodium atmosphere. The leak path was plugged by the sodium-water reaction products in the 2.25Cr-1Mo steel specimen. However, leak paths re-opened in most cases. The self-wastage patterns were not affected by the sodium temperature in the re-opened specimen. The diameter of the defected area, including the re-opened part, was about 5 min. It took 143, 40.7 and 34.7 minutes to re-open the leak path at 450, 475, and 510 ℃, respectively. It was concluded that the reopening time decreased with the increasing temperature.

Keywords:Self-wastage;Reopening time;Sodium-water reaction

[References]

石神努, 小林健介, 日本原子力學會誌, 35, 549 (1993)
Anderson R, Nucl. Energy, 18, 333 (1979)
Tanabe H, Wachi E, IAEA/IWGFR Specialists' Meeting on "Steam Generator: Failure and Failure Propagation," Aixen-Provence, Sept. 26, France (1990)
Chamberlain HV, Cameron JA, Ford JA, APDA Report 254 (1968)
Nei H, J. Nucl. Sci. Technol., 14, 652 (1997)
Newman RN, Smith CA, J. Nucl. Mater., 52, 173 (1974)
宇佐美正行, 下山一仁, 田邊裕美, 嬉野嘉昭, 日本原子力學會誌, 33, 363 (1991)
Casey DF, Trans. ANS, 19, 316 (1974)
Voss J, Vagt P, von Westenbrugge JK, Joziasse J, Report-IWGFR/50, 79 (1983)
Kanegae N, Hashiguchi K, Ikemoto I, Hori M, Trans. ANS, 24, 386 (1976)
Currie R, Innes N, Fraser AS, LIMET '88, Proceedings 4th Inter. Conf., Liquid Metal Engineering Technology, Avignon, France (1988)
Shin YW, Berry GF, Daley JG, Trans. Int. Conf. Structural Mechanical Reaction Technology, Paper B8 (1981)
Sane JO, Regimbal JJ, Fairbairn JA, Meyer RA, Proceedings of the Inter. Meeting of Fast Reactor Safety Technology, 4, 1878 ~ 1887, Seattle (1979)
Bae JH, Shin MC, Korea Nucl. Soc., 30, 568 (1998)
Payne JFB, Nucl. Energy, 19, 303 (1980)
Jeong KC, Jeong JY, Park JH, Hwang ST, Kim ES, J. Korean Ind. Eng. Chem., 9(7), 1023 (1998)
Quinet JL, Lannou L, Nucl. Technol., 46, 582 (1979)

[Referenced By]

[1] 石神努, 小林健介, 日本原子力學會誌, 35, 549 (1993)

[2] Anderson R, Nucl. Energy, 18, 333 (1979)

[3] Tanabe H, Wachi E, IAEA/IWGFR Specialists' Meeting on "Steam Generator: Failure and Failure Propagation," Aixen-Provence, Sept. 26, France (1990)

[4] Chamberlain HV, Cameron JA, Ford JA, APDA Report 254 (1968)

[5] Nei H, J. Nucl. Sci. Technol., 14, 652 (1997)

[6] Newman RN, Smith CA, J. Nucl. Mater., 52, 173 (1974)

[7] 宇佐美正行, 下山一仁, 田邊裕美, 嬉野嘉昭, 日本原子力學會誌, 33, 363 (1991)

[8] Casey DF, Trans. ANS, 19, 316 (1974)

[9] Voss J, Vagt P, von Westenbrugge JK, Joziasse J, Report-IWGFR/50, 79 (1983)

[10] Kanegae N, Hashiguchi K, Ikemoto I, Hori M, Trans. ANS, 24, 386 (1976)

[11] Currie R, Innes N, Fraser AS, LIMET '88, Proceedings 4th Inter. Conf., Liquid Metal Engineering Technology, Avignon, France (1988)

[12] Shin YW, Berry GF, Daley JG, Trans. Int. Conf. Structural Mechanical Reaction Technology, Paper B8 (1981)

[13] Sane JO, Regimbal JJ, Fairbairn JA, Meyer RA, Proceedings of the Inter. Meeting of Fast Reactor Safety Technology, 4, 1878 ~ 1887, Seattle (1979)

[14] Bae JH, Shin MC, Korea Nucl. Soc., 30, 568 (1998)

[15] Payne JFB, Nucl. Energy, 19, 303 (1980)

[16] Jeong KC, Jeong JY, Park JH, Hwang ST, Kim ES, J. Korean Ind. Eng. Chem., 9(7), 1023 (1998)

[17] Quinet JL, Lannou L, Nucl. Technol., 46, 582 (1979)