Abstract
In the occluded volume of high temperature pressurized water loop in nuclear power plants, poor-controlled water chemistry due to sluggish flowage could induce accelerated degradation of structural materials. In this paper, an occluded volume shaped nuclear-grade 304 stainless steel sample was immersed in oxygenated high temperature water containing a certain concentration of Ni2+. It was found that from the outer to the inner side of the sample, the proportion of spinel in the oxide film decreased while that of hematite increased and Ni content in the outer oxide film decreased. It was thought that the concentration of Ni2+ could influence the oxidation behavior of material significantly. The occluded volume could impede the inward diffusion of Ni2+, causing a concentration gradient of Ni2+ along depth of the volume and gradual change of oxide film characteristic.
| Original language | English |
|---|---|
| Pages (from-to) | 927-931 |
| Number of pages | 5 |
| Journal | Jinshu Xuebao/Acta Metallurgica Sinica |
| Volume | 47 |
| Issue number | 7 |
| DOIs | |
| State | Published - Jul 2011 |
| Externally published | Yes |
Keywords
- High temperature high pressure water
- Ni
- Nuclear-grade stainless steel
- Occluded volume
- Oxide film
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