首页> 外文会议>Powder Metallurgy World Congress amp; Exhibition(PM 2006); 20060924-28; Busan(KR) >SCC Inhibitors for SG Tube Materials in Nuclear Power Plants
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SCC Inhibitors for SG Tube Materials in Nuclear Power Plants

机译:核电站SG管材料的SCC抑制剂

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Several chemicals were studied to suppress the damage due to stress corrosion cracking (SCC) of steam generator (SG) tubes in nuclear power plants. The polarization curves showed that the electrochemical properties on the surface of Alloy 600 MA changed with the addition of inhibitors. The SCC tests were conducted by using a m-RUB specimen in a 10% NaOH solution at a temperature of 315 ℃. The effects on the SCC of the compounds, TiO_2, TyzorLA and CeB_6, were tested for several types of SG tubing materials. The test with the addition of TiO_2 (P25) and CeE$6 showed an effect in decreasing the SCC for the SG tubing material. However, CeB_6 caused some more SCC for Alloy 800. The penetration property into a crevice of the inhibitors was investigated by using Alloy 600 specimens with different gap sizes and an AES analysis was performed on the oxide layer of the specimen.
机译:对几种化学物质进行了研究,以抑制核电站中蒸汽发生器(SG)管的应力腐蚀开裂(SCC)造成的损坏。极化曲线表明,添加抑制剂后,合金600 MA表面的电化学性能发生了变化。通过使用m-RUB样品在315℃的10%NaOH溶液中进行SCC测试。对于几种类型的SG管材,测试了化合物TiO_2,TyzorLA和CeB_6对SCC的影响。添加TiO_2(P25)和CeE $ 6的测试显示出降低SG管材的SCC的效果。但是,CeB_6对800合金造成了更多的SCC。使用具有不同间隙尺寸的600合金样品研究了抑制剂在缝隙中的渗透性能,并对样品的氧化物层进行了AES分析。

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