(A) study on the lifetime estimation of the nuclear reactor pressure vessel on the basis of fracture mechanics파괴 역학적 관점에서 원자로 압력용기의 수명예측에 관한 연구

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dc.contributor.advisorKim, In-Sup-
dc.contributor.advisor김인섭-
dc.contributor.authorJang, Kag-Su-
dc.contributor.author장각수-
dc.date.accessioned2011-12-14T08:13:07Z-
dc.date.available2011-12-14T08:13:07Z-
dc.date.issued1989-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=67577&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/49244-
dc.description학위논문(석사) - 한국과학기술원 : 핵공학과, 1989, [ iii, 48 p. ]-
dc.description.abstractThe lifetime estimation of the nuclear reactor pressure vessel is studied on the basis of fracture mechanics. Since the recent interest in the plant life extension for the light water reactor has increased, it is important one to evaluate the engineering lifetime of major equipments or components used in nuclear power plants. Major factors which have to be taken into consideration in plant lifetime estimation are : (a) the growth trend of potential defects in components due to subcritical crack growth caused by synergistic effects of environmental attack and operating loading. (b) materials degradation after long term operation in the thermal and/or radiation embrittlement. The estimated lifetime is the cross cut point between applied stress intensity ($k_{APPLIED}$) caused by the crack growth and fracture toughness degradation ($K_{ICIRR}$) caused by the irradiation. It is the sensitive for lifetime of the each cases of initial crack length, frequency, stress intensity and stress intensity and stress variable, and has a example for HSST weld metal. The stress intensity variable is more important than others and the estimated liftime is between $1.117\times10^6$(2.13 years) and $1.056\times10^8$(200 years) minutes.eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.title(A) study on the lifetime estimation of the nuclear reactor pressure vessel on the basis of fracture mechanics-
dc.title.alternative파괴 역학적 관점에서 원자로 압력용기의 수명예측에 관한 연구-
dc.typeThesis(Master)-
dc.identifier.CNRN67577/325007-
dc.description.department한국과학기술원 : 핵공학과, -
dc.identifier.uid000881411-
dc.contributor.localauthorJang, Kag-Su-
dc.contributor.localauthor장각수-
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NE-Theses_Master(석사논문)
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