Corrosion of 316L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits
Corrosion of 316L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits
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316L 暴露于核聚变实验反应堆冷却回路中用作屏蔽的高浓度硼酸水中的腐蚀
DOI：
10.1016/j.corsci.2024.111902
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发表时间：
2024
影响因子：
8.3
通讯作者：
Gasparrini C
中科院分区：
文献类型：
--
作者：
Gasparrini C
含硼水在核聚变冷却回路中用作屏蔽。测试了316 L钢在80 °C下暴露于超纯水（UPW）或8000 ppm B水时的全面腐蚀、活化腐蚀产物（ACP）形成和应力腐蚀开裂起始。使用高级表征（STEM-EELS，APT）观察到Ni富集的亚氧化层、过渡层和氧化层。在UPW中形成的氧化物是保护性的（Cr：O 40：45），在8000 ppm B中形成的氧化物是非钝化性的。8000 ppm的B导致Fe、Cr和Mo的释放量增加，316 L更容易引发SCC并促进ACP的形成。
Borated water is used as a shield in nuclear fusion cooling circuits. General corrosion, activated corrosion products (ACPs) formation and stress corrosion cracking initiation of 316 L steels exposed to ultrapure water (UPW) or 8000 ppm B water at 80 °C were tested. A Ni enriched sub-oxide layer, a transition layer and oxide layer were observed using advanced characterisation (STEM-EELS, APT). The oxide formed in UPW was protective (Cr:O 40:45), the oxide formed in 8000 ppm B was non-passivating. 8000 ppm B led to higher release of Fe, Cr and Mo, 316 L was more prone to SCC initiation and enhanced ACPs formation.