The influence of the Cr content on oxidation behaviors of Ni-base Alloys in PWR primary water

机译：Cr含量对PWR一次水中Ni基合金氧化行为的影响

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The effect of chromium content in Ni(bal.)-Cr(16,19,22,25,30)％-9％Fe alloys on corrosion behaviors in PWR primary coolant was investigated in this work.Corrosion test was carried out in simulating PWR primary water at 330℃.Corrosion rate decreased parabolically with the increase of Cr content and showed the similar value for the Ni-Cr-Fe alloys including the Cr content more than 22 wt.％.

机译：研究了Ni（bal。）-Cr（16,19,22,25,30）％-9％Fe合金中铬含量对压水堆一次冷却剂腐蚀行为的影响。在模拟中进行了腐蚀试验压水堆（PWR）在330℃时为原水。腐蚀速率随Cr含量的增加呈抛物线下降，并且当Cr含量大于22 wt。％时，Ni-Cr-Fe合金的腐蚀速率与之相似。

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《5th International Symposium on Materials and Reliability in Nuclear Power Plants amp; Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia-2017 amp; 3rd Asian Forum on Material Aging I》|2017年|189|共1页
会议地点 Shenyang (CN)
作者
Hee-Sang Shim; Hyun-Jin Cha; Do Haeng Hur;
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Materials Research Division,KAERI,989-111 Daedeok-daero,Yuseong-gu,Daejeon 34057,Republic of Korea;

Materials Research Division,KAERI,989-111 Daedeok-daero,Yuseong-gu,Daejeon 34057,Republic of Korea;

Materials Research Division,KAERI,989-111 Daedeok-daero,Yuseong-gu,Daejeon 34057,Republic of Korea;

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正文语种 eng
中图分类电工技术;原子能技术;
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3. Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water: Effect of Chromium Content in Alloys and Dissolved Hydrogen [J] . Takumi TERACHI, Takuyo YAMADA, Tomoki MIYAMOTO, Journal of nuclear science and technology . 2008,第10期

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4. The influence of the Cr content on oxidation behaviors of Ni-base Alloys in PWR primary water [C] . Hee-Sang Shim, Hyun-Jin Cha, Do Haeng Hur Asian forum on material aging issues in nuclear system . 2017

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5. High Temperature Corrosion Behaviour of Ni-Base Alloys and FeCrAl Alloys – the Influence of Water Vapour [D] . Sand, Tommy. 2019

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The influence of the Cr content on oxidation behaviors of Ni-base Alloys in PWR primary water

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