Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

Jian Li; W. Zheng; Sami Penttilä; P. Liu; O.T. Woo; D. Guzonas

doi:10.1016/j.jnucmat.2014.06.043

Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

Jian Li (Corresponding Author), W. Zheng, Sami Penttilä, P. Liu, O.T. Woo, D. Guzonas

Research output: Contribution to journal › Article › Scientific › peer-review

25 Citations (Scopus)

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.

Original language	English
Pages (from-to)	7-11
Journal	Journal of Nuclear Materials
Volume	454
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2014.06.043
Publication status	Published - 2014
MoE publication type	A1 Journal article-refereed

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title = "Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application",

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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AU - Li, Jian

AU - Zheng, W.

AU - Penttilä, Sami

AU - Liu, P.

AU - Woo, O.T.

AU - Guzonas, D.

PY - 2014

Y1 - 2014

N2 - 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.

AB - 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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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

Abstract

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