Evaluation of the Effect of Thermal Ageing of Austenitic Stainless Steel Welds in PWRs = 가동 원전 오스테나이트계 스테인리스강 용접부의 열취화에 대한 영향 평가

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dc.contributor.advisorJang, Changheui-
dc.contributor.advisor장창희-
dc.contributor.authorHong, Sunghoon-
dc.date.accessioned2018-06-20T06:20:32Z-
dc.date.available2018-06-20T06:20:32Z-
dc.date.issued2017-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=675330&flag=dissertationen_US
dc.identifier.urihttp://hdl.handle.net/10203/243201-
dc.description학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2017.2,[iv, 57 p. :]-
dc.description.abstractThree austenitic stainless steel welds (ASSW), such as E308, ER316L and ER347, with about 10 % of δ-ferrite were thermally aged at $400^\circ C$ up to 20,000 h to accelerate the thermal ageing expected in pressurized water reactor (PWR) environment. Fluctuation of Fe and Cr due to spinodal decomposition is observed with width of 5 - 12 nm within the ferrite phase. For all 3 welds, increase in strength and decrease in tensile elongation is observed after thermal aging at room temperature and $320^\circ C$. The reduction in fracture resistance, measured as J-R curves, is most significant for ER316L weld with decrease by about 61%. However, it is quite small (about 25 % decrease) for ER347 weld even after ageing at $400^\circ C$ for 20,000 h despite the large reduction in tensile elongation. Finally, the double loop-electrochemical potentiodynamic reactivation (DL-EPR) tests show the degree of sensitization (DOS) values are negligible even after the accelerated thermal ageing at $400^\circ C$ for 10,000 h.-
dc.languageeng-
dc.publisher한국과학기술원-
dc.subjectaustenitic stainless steel welds-
dc.subjectthermal ageing-
dc.subjectJ-R curve-
dc.subjectsensitization-
dc.subjectmechanical properties-
dc.subject오스테나이트계 스테인리스강 용접부-
dc.subject열취화-
dc.subjectJ-R 시험-
dc.subject부식 특성-
dc.subject기계적 물성-
dc.titleEvaluation of the Effect of Thermal Ageing of Austenitic Stainless Steel Welds in PWRs = 가동 원전 오스테나이트계 스테인리스강 용접부의 열취화에 대한 영향 평가-
dc.typeThesis(Master)-
dc.identifier.CNRN325007-
dc.description.department한국과학기술원 :원자력및양자공학과,-
dc.contributor.alternativeauthor홍성훈-
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NE-Theses_Master(석사논문)
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