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Thermal Stability of Microstructure in Grain Boundary Character Distribution-Optimized and Cold-Worked Austenitic Stainless Steel Developed for Nuclear Reactor Application

Published online by Cambridge University Press:  31 January 2011

Shinichiro Yamashita ,
Yasuhide Yano ,
Ryusuke Tanikawa ,
Norihito Sakaguchi ,
Seiichi Watanabe ,
Masanori Miyagi ,
Shinya Sato  and
Hiroyuki Kokawa
Shinichiro Yamashita
Affiliation:
yamashita.shinichiro@jaea.go.jpyamashi5034@yahoo.co.jp, Japan Atomic Energy Agency, Fuels and Materials Department, Ibaraki, Japan
Yasuhide Yano
Affiliation:
yano.yasuhide@jaea.go.jp, Japan Atomic Energy Agency, Fuels and Materials Department, Ibaraki, Japan
Ryusuke Tanikawa
Affiliation:
tanikawa@ufml.caret.hokudai.ac.jp, Hokkaido University, Center for Advanced Research of Energy Conversion Materials, Sapporo, Japan
Norihito Sakaguchi
Affiliation:
sakagu@ufml.caret.hokudai.ac.jp, Hokkaido University, Center for Advanced Research of Energy Conversion Materials, Sapporo, Japan
Seiichi Watanabe
Affiliation:
sw004@eng.hokudai.ac.jp, Hokkaido University, Center for Advanced Research of Energy Conversion Materials, Sapporo, Japan
Masanori Miyagi
Affiliation:
a6tm5626@stu.material.tohoku.ac.jp, Tohoku University, Department of Materials Processing, Sendai, Japan
Shinya Sato
Affiliation:
a7tm5615@stu.material.tohoku.ac.jp, Tohoku University, Department of Materials Processing, Sendai, Japan
Hiroyuki Kokawa
Affiliation:
kokawa@material.tohoku.ac.jp, Tohoku University, Department of Materials Processing, Sendai, Japan
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Abstract

Grain boundary character distribution-optimized (GBCD) Type 316 corresponding austenitic stainless steel and its cold-worked ones (GBCD+CW) are one of prospective nuclear materials to be considered for next generation energy systems. These steels were thermally-aged at 973 K for 1 and 100 h and were examined by transmission electron microscopy (TEM) to evaluate microstructural stability during high temperature exposure. TEM results revealed that microstructures of both specimens prior to ageing contained step-wise boundaries which is composed of coincidence site lattice (CSL) and random grain boundaries and also that the GBCD+CW specimens had dislocation cells and networks as well as deformation twins whereas as the GBCD one possessed few dislocations. After thermal ageing, the precipitates formed on not only random grain boundaries but also dislocations, contributing to prevent significant microstructural change occurring such as recrystallization and dislocation recovery.

Keywords

nuclear materialsgrain boundariesmicrostructure
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1215: Symposium V – Materials Research Needs to Advance Nuclear Energy , 2009 , 1215-V16-15
Copyright
Copyright © Materials Research Society 2010

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