Study on Corrosion of Alloy 800 in PWR Primary Water

QIAO Pei-peng; ZHANG Le-fu; LIU Rui-qin; ZHU Fa-wen

Oct. 2010

Article Contents

Article Navigation > Nuclear Power Engineering > 2010 > 31(5): 28-31

QIAO Pei-peng, ZHANG Le-fu, LIU Rui-qin, ZHU Fa-wen. Study on Corrosion of Alloy 800 in PWR Primary Water[J]. Nuclear Power Engineering, 2010, 31(5): 28-31.

Citation:

QIAO Pei-peng, ZHANG Le-fu, LIU Rui-qin, ZHU Fa-wen. Study on Corrosion of Alloy 800 in PWR Primary Water[J]. Nuclear Power Engineering, 2010, 31(5): 28-31.

QIAO Pei-peng, ZHANG Le-fu, LIU Rui-qin, ZHU Fa-wen. Study on Corrosion of Alloy 800 in PWR Primary Water[J]. Nuclear Power Engineering, 2010, 31(5): 28-31.

Citation:

QIAO Pei-peng, ZHANG Le-fu, LIU Rui-qin, ZHU Fa-wen. Study on Corrosion of Alloy 800 in PWR Primary Water[J]. Nuclear Power Engineering, 2010, 31(5): 28-31.

PDF( 356 KB)

Study on Corrosion of Alloy 800 in PWR Primary Water

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

Received Date: 2009-07-23
Rev Recd Date: 2009-10-23

Available Online: 2025-07-31

Abstract

Abstract

The corrosion behavior of Alloy 800 was investigated in the high-oxygen solution containing 600 mg/kg boron and 2 mg/kg lithium for 1500 h at 320℃.The results showed that the general corrosion rate of Alloy 800 after 1500 h was 4.03×10^-4 mm/a,and the oxide film layer was very thin.The TiN precipitates in the matrix could result in pitting.Intergranular attack could be found in the inner side of the tubular specimens after exposure for 1500 h.
- General corrosion rate,
- Intergranular attack,
- Pitting,
- Alloy 800,
- Steam generator heat exch-ange tube