Irradiation characteristics of metal-based accident resistant fuel cladding = 사고저항성 금속 연료 피복관의 방사선 조사 전 후 물성 평가

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Recently, stainless steel is being developed to replace the zirconium alloy that caused the 2011 Fukushima nuclear accident. The newly developed cladding require various properties such as high strength and ductility, oxidation resistance, and corrosion resistance. In order to investigate the radiation resistance, which is an important requirement of the cladding material, the properties should be measured by irradiating neutron as in the reactor core. However, neutron studies on all the specimens under development have many limitations. Therefore, in this study, we propose neutron irradiation preliminary experiment by proton irradiation, using phase analysis with SEM and TEM, and physical property measurement through nanoindentation.
Advisors
Jang, Dongchanresearcher장동찬researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2019
Identifier
325007
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2019.2,[iii, 26 p. :]

Keywords

radiation tolerance▼aneutron▼aproton▼aSEM▼aTEM▼ananoindentation; 방사선 저항성▼a중성자▼a양성자▼aSEM▼aTEM▼a나노인덴테이션

URI
http://hdl.handle.net/10203/266573
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=843357&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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