Analysis of micro-leak sodium-water reaction phenomena in a sodium-cooled fast reactor steam generator

Ji-Young Jeong; Tae-Joon Kim; Jong-Man Kim; Byoung-Ho Kim; Nam-Cook Park

Korean Journal of Chemical Engineering, Vol.26, No.4, 1004-1008, July, 2009

DOI10.1007/s11814-009-0167-x Export Citation

Analysis of micro-leak sodium-water reaction phenomena in a sodium-cooled fast reactor steam generator

Ji-Young Jeong^†, Tae-Joon Kim, Jong-Man Kim, Byoung-Ho Kim, and Nam-Cook Park¹

Fast Reactor Technology Development Division, Korea Atomic Energy Research Institute, Korea
¹Chemical Engineering Division, Chonnam National University, Korea

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The effects of the sodium-water reaction by small water/steam leaks on 2.25Cr-1Mo and Mod.9Cr-1Mo steels have been studied. Test specimens were exposed to small leaks of water/steam in 300 ℃ stagnant sodium. The phenomenon where the size of the nozzle hole became larger with time was observed for the two types of material. Enlargement rate was slightly faster in the 2.25Cr-1Mo steel than in the Mod.9Cr-1Mo steel. Test results of the enlargement rate of the nozzle hole itself with an increasing duration of the steam injection were analyzed by using SEM and CAMSCOPE images. The maximum reaction temperature appeared at a 17 mm point from the measuring tool, which agrees with the maximum distance that was affected by a jet flame.

Keywords:Sodium-water Reaction;Small Leak;Sodium-cooled Fast Reactor;Steam Generator;Wastage;Self-wastage

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Jeong KC, Jeong JY, Kim BH, Kim TJ, Choi JH, J. Ind. Eng. Chem., 8(3), 283 (2002)
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Judd AM, Currie R, Linekar GAB, Henderson JDC, Nucl. Energ.-J. BR Nucl., 31, 221 (1992)
Eoh JH, Jeong JY, Kim SO, Hahn DH, Nucl. Technol., 152, 287 (2005)
Hans R, Dumm K, Atomic Energy Review, 154, 611 (1977)
Roger F, Park KY, Larreau JL, Gbahoue L, Hobbes P, CEACONF-7851 (1984)
Okano Y, Yamaguchi A, INIS-FR-483 (2001)
Dumm K, IWGFR-1, C.8 (1975)

[Related Articles]

[1] Hori M, Atomic Energy Review, 18, 708 (1980)

[2] Jeong KC, Jeong JY, Kim BH, Kim TJ, Choi JH, Hahn DH, Kim ES, J. Ind. Eng. Chem., 10(4), 524 (2004)

[3] Jeong KC, Jeong JY, Kim BH, Kim TJ, Choi JH, J. Ind. Eng. Chem., 8(3), 283 (2002)

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

[5] Kanegae N, Hashiguchi K, Ikemoto I, Hori M, Nucl. Technol., 40, 261 (1978)

[6] Pugh AR, Nucl. Energ.-J. BR Nucl., 11, 263 (1972)

[7] Donati JR, Grand M, Spiteri P, J. Nucl. Mater., 54, 217 (1974)

[8] Sandusky DW, Trans. ANS, 19, 106 (1974)

[9] Payne JFB, Nucl. Energ.-J. BR Nucl., 18, 327 (1979)

[10] Judd AM, Currie R, Linekar GAB, Henderson JDC, Nucl. Energ.-J. BR Nucl., 31, 221 (1992)

[11] Eoh JH, Jeong JY, Kim SO, Hahn DH, Nucl. Technol., 152, 287 (2005)

[12] Hans R, Dumm K, Atomic Energy Review, 154, 611 (1977)

[13] Roger F, Park KY, Larreau JL, Gbahoue L, Hobbes P, CEACONF-7851 (1984)

[14] Okano Y, Yamaguchi A, INIS-FR-483 (2001)

[15] Dumm K, IWGFR-1, C.8 (1975)