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

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

Research output: Contribution to journalArticleScientificpeer-review

21 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 languageEnglish
Pages (from-to)7-11
Number of pages5
JournalJournal of Nuclear Materials
Volume454
Issue number1-3
DOIs
Publication statusPublished - 2014
MoE publication typeA1 Journal article-refereed

Fingerprint

Stainless Steel
stainless steels
Stainless steel
corrosion resistance
microstructure
Microstructure
Corrosion resistance
materials selection
stress corrosion cracking
creep strength
Creep resistance
embrittlement
Embrittlement
Stress corrosion cracking
austenite
Austenite
corrosion
reactors
mechanical properties
Corrosion

Cite this

Li, J ; Zheng, W ; Penttilä, Sami ; Liu, P ; Woo, O T ; Guzonas, D. / Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application. In: Journal of Nuclear Materials. 2014 ; Vol. 454, No. 1-3. pp. 7-11.
@article{093bba0d244a4623abcebb843e97daf8,
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.",
author = "J Li and W Zheng and Sami Penttil{\"a} and P Liu and Woo, {O T} and D Guzonas",
year = "2014",
doi = "10.1016/j.jnucmat.2014.06.043",
language = "English",
volume = "454",
pages = "7--11",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",
number = "1-3",

}

Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application. / Li, J (Corresponding Author); Zheng, W; Penttilä, Sami; Liu, P; Woo, O T; Guzonas, D.

In: Journal of Nuclear Materials, Vol. 454, No. 1-3, 2014, p. 7-11.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

AU - Li, J

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.

U2 - 10.1016/j.jnucmat.2014.06.043

DO - 10.1016/j.jnucmat.2014.06.043

M3 - Article

VL - 454

SP - 7

EP - 11

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

IS - 1-3

ER -