DC Field | Value | Language |
---|---|---|
dc.contributor.advisor | Jang, Changheui | - |
dc.contributor.advisor | 장창희 | - |
dc.contributor.author | Shin, Ji Ho | - |
dc.date.accessioned | 2019-09-03T02:47:49Z | - |
dc.date.available | 2019-09-03T02:47:49Z | - |
dc.date.issued | 2018 | - |
dc.identifier.uri | http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=733943&flag=dissertation | en_US |
dc.identifier.uri | http://hdl.handle.net/10203/266574 | - |
dc.description | 학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2018.2,[v, 61 p. :] | - |
dc.description.abstract | A set of irradiation resistant austenitic stainless steels were developed utilizing the thermodynamic calculation and thermo-mechanical processing (TMP) for the potential application as nuclear reactor internals materials. The chemical composition was set to have the advantages of phase stability according to the temperature, irradiation and corrosion resistant characteristics. Stepwise heat treatment was performed in order to precipitate fine titanium nitride and niobium carbide at high temperature ($> 850^\circ C$). In the case of TiN, the volume fraction was not so large, but it contributed to grain size refinement by pinning effect. Meanwhile, the volume fraction of fine NbC was large enough to achieve irradiation resistance by providing a large amount of sink sites such as phase boundaries. Cold rolling and re-crystallization heat treatment was carried out to further increase the amount of dislocation and grain boundary which act as sink sites. Finally, the mechanical properties and calculated sink strength were compared in view of the alloy composition and subsequent TMP. | - |
dc.language | eng | - |
dc.publisher | 한국과학기술원 | - |
dc.subject | Advanced radiation resistant austenitic alloy▼aFine precipitates▼aGrain size refinement▼aThermo-mechanical processing▼aSink site▼aMechanical properties | - |
dc.subject | 조사저항성을 갖는 합금 개발▼a미세 석출물▼a결정립 크기 미세화▼a열-기계적 공정▼a싱크사이트▼a기계적 물성 | - |
dc.title | Development and mechanical property evaluation of Ti, Nb-modified advanced radiation resistant austenitic ($AR^2A$) alloys for reactor internals | - |
dc.title.alternative | 조사저항성을 갖는 원자로 내부 구조물용 오스테니틱 합금 개발 및 기계적 특성 평가 | - |
dc.type | Thesis(Master) | - |
dc.identifier.CNRN | 325007 | - |
dc.description.department | 한국과학기술원 :원자력및양자공학과, | - |
dc.contributor.alternativeauthor | 신지호 | - |
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