Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7967127 | Journal of Nuclear Materials | 2014 | 10 Pages |
Abstract
In the past few years, significant progress has been made in materials selection for Gen-IV SCWR fuel cladding applications. Current studies indicate that austenite stainless steels such as 310H are promising candidates for in-core applications. Alloys in this group are promising for their corrosion resistance, SCC resistance, high temperature mechanical properties and creep resistance at temperatures up to 700 °C. However, one under-studied area of this alloy is the long-term microstructure stability under the proposed reactor operating condition. Unstable microstructure not only results in embrittlement but also has the potential to reduce their resistance to corrosion or stress-corrosion cracking. In this study, stainless steels 310H and 304H were tested for their SCWR corrosion resistance and microstructure stability.
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Authors
Jian Li, W. Zheng, S. Penttilä, P. Liu, O.T. Woo, D. Guzonas,