Development of nano carbide dispersed advanced radiation resistant austenitic stainless steels (NC-ARES) for reactor internals조사저항성을 갖는 원자로 내부 구조물용 오스테니틱 스테인리스 합금 개발

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Austenitic stainless steels (SSs) are widely used as in-core materials in current nuclear systems, with combination of good corrosion resistance, ductility, and mechanical properties. Meanwhile, they subjected to high neutron fluence of typically up to 70‒100 displacement per atom during operating time period of more than 40 years. However, the neutron irradiation causes deleterious effect on the microstructural evolution which effects on mechanical properties such as irradiation hardening and embrittlement. Especially, austenitic SSs are highly susceptible due to poor void swelling resistance, which would be a life-limiting degradation for reactor internal components. Therefore, development of advanced nuclear reactors with longer lifetime and better efficiency requires advanced materials that can withstand higher irradiation dose. In this thesis, an austenitic SS with uniformly distributed nanosized NbC precipitates, named as ARES-6P, was developed, by controlling chemical composition and thermo-mechanical processing. Then, the strengthening effects of the uniformly distributed nanosized NbC precipitates were evaluated using the micropillar compression test. Finally, the swelling resistance of the newly developed ARES-6P was investigated using the heavy ion irradiation and the results were compared with commercial 316 SS.
Advisors
Jang, Changheuiresearcher장창희researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2022
Identifier
325007
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2022.2,[xiv, 166 p. :]

URI
http://hdl.handle.net/10203/308672
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=996283&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
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