Study on application of higher-order numerical scheme to 1-D thermal-hydraulic system analysis code1D 열수력 시스템 해석 코드의 고차 수치해석 방법 적용성 연구

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dc.contributor.advisorLee, Jeong Ik-
dc.contributor.advisor이정익-
dc.contributor.authorLee, Won Woong-
dc.contributor.author이원웅-
dc.date.accessioned2017-03-29T02:36:18Z-
dc.date.available2017-03-29T02:36:18Z-
dc.date.issued2016-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=649564&flag=dissertationen_US
dc.identifier.urihttp://hdl.handle.net/10203/221633-
dc.description학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2016.2 ,[ix, 71 p. :]-
dc.description.abstractThe existing nuclear system analysis codes such as RELAP5, TRAC, MARS and SPACE use the first-order numerical scheme in both space and time discretization. However, the first-order scheme is highly diffusive and less accurate due to the first order of truncation error. Nowadays, the nuclear system analysis code requires higher accuracy for the prediction of the nuclear system safety and therefore, a nuclear reactor system analysis code with better performance is needed in nuclear industry. Thus, this study evaluated the application of the higher-order numerical scheme for the next generation nuclear system analysis code. In this study, to identify effects of numerical diffusion and dispersion problem and the decreasing error depending on the increasing mesh number, single phase pipe flow simulation with a sine pulse of temperature was conducted. The calculation was performed with MARS and a separate single phase transient analysis code, namely NTS code, which is possible to calculate in the first-order and the higher-order schemes but mimics MARS solver built in MATLAB environment. In addition, to evaluate sensitivity of the results to the input perturbation in the first-order and second-order schemes, simplified primary loop of nuclear reactor system simulation was performed by MARS and NTS codes. Through this study, the numerical diffusion and dispersion problems in the numerical methods were observed in a single phase transient analysis code. In addition, it is identified that the numerical diffusion and dispersion problems result in numerical instabilities and non-physical solutions. Therefore, to stabilize the numerical solutions of the higher-order scheme and to obtain more precise solutions, a slope limiter should be applied or more stable higher-order scheme should be implemented. Furthermore, these attempts should be identified whether more stable and accurate solutions can be obtained under the two phase flow conditions in the future.-
dc.languageeng-
dc.publisher한국과학기술원-
dc.subjectNumerical scheme-
dc.subjectfirst-order-
dc.subjecthigher-order-
dc.subjectupwind scheme-
dc.subjectMARS-
dc.subjectnumerical diffusion-
dc.subjectnumerical dispersion-
dc.subjectsingle-phase-
dc.subjectnuclear system analysis code-
dc.subject1차 수치해석 방법-
dc.subject고차 수치해석 방법-
dc.subject풍상 차분법-
dc.subject수치적 확산-
dc.subject수치적 분산-
dc.subject단상 유동-
dc.subject원자력 시스템 해석 코드-
dc.titleStudy on application of higher-order numerical scheme to 1-D thermal-hydraulic system analysis code-
dc.title.alternative1D 열수력 시스템 해석 코드의 고차 수치해석 방법 적용성 연구-
dc.typeThesis(Master)-
dc.identifier.CNRN325007-
dc.description.department한국과학기술원 :원자력및양자공학과,-
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NE-Theses_Master(석사논문)
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