LAPUR穩定性分析方法論的自動化設計

碩士 === 國立清華大學 === 工程與系統科學系 === 97 === Under certain conditions, boiling water reactors (BWRs) are susceptible to coupled neutronic/thermal-hydraulic instabilities. Such instabilities, which are characterized by periodic core power and hydraulic oscillations, can compromise established fuel safety li...

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Main Authors: Li, Hsuan-Nien, 李宣年
Other Authors: Shih, Chunkuan
Format: Others
Language:zh-TW
Published: 2009
Online Access:http://ndltd.ncl.edu.tw/handle/91799516243684515542
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spelling ndltd-TW-097NTHU55930182015-10-13T14:52:52Z http://ndltd.ncl.edu.tw/handle/91799516243684515542 LAPUR穩定性分析方法論的自動化設計 Li, Hsuan-Nien 李宣年 碩士 國立清華大學 工程與系統科學系 97 Under certain conditions, boiling water reactors (BWRs) are susceptible to coupled neutronic/thermal-hydraulic instabilities. Such instabilities, which are characterized by periodic core power and hydraulic oscillations, can compromise established fuel safety limits. There are two types of reactivity instabilities have been observed in commercial BWRs: A. Core-wide reactivity instabilities; B. Out of phase instabilities. In both cases, the reactivity instability is caused by the density wave mechanism, which is reinforced by feedbacks from neutronic power and channel inlet flow. LAPUR is a computer code developed at Oak Ridge National Laboratory for the calculation of BWR core stability parameters. It uses a multinodal description of the neutron dynamics, together with a distributed parameter model of the core thermal hydrodynamics to produce a space-dependent representation of the dynamics of a BWR in the frequency domain for small perturbations around a steady state condition. The LAPUR program consists of two autonomous modules, LAPURX and LAPURW, which are linked by means of an intermediate storage routine. The first module, LAPURX, solves the governing equations for the coolant and the fuel steady state. Map of the core steady state are generated and stored in data files for subsequent utilization by LAPURW. The second module, LAPURW, solves the dynamic equations for the coolant, fuel, and neutron field in the frequency domain. A set of open-loop transfer functions are generated and the stability index (decay ratio), is estimated from the closed loop reactivity to power transfer function. Today, personal computers are cheaper and powerful. With its faster and faster computing ability, we can dispatch PC to calculate the routine work, like the repeating parameter testes. In this paper, we use programming skills and loop concepts on LAPUR DR calculation, in order to saving human power on parameter testing. We expect that this method can provide a simple way to those who concentrate on parametric studies, and get a large mount, more and more reliable data easily. Shih, Chunkuan 施純寬 2009 學位論文 ; thesis 114 zh-TW
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description 碩士 === 國立清華大學 === 工程與系統科學系 === 97 === Under certain conditions, boiling water reactors (BWRs) are susceptible to coupled neutronic/thermal-hydraulic instabilities. Such instabilities, which are characterized by periodic core power and hydraulic oscillations, can compromise established fuel safety limits. There are two types of reactivity instabilities have been observed in commercial BWRs: A. Core-wide reactivity instabilities; B. Out of phase instabilities. In both cases, the reactivity instability is caused by the density wave mechanism, which is reinforced by feedbacks from neutronic power and channel inlet flow. LAPUR is a computer code developed at Oak Ridge National Laboratory for the calculation of BWR core stability parameters. It uses a multinodal description of the neutron dynamics, together with a distributed parameter model of the core thermal hydrodynamics to produce a space-dependent representation of the dynamics of a BWR in the frequency domain for small perturbations around a steady state condition. The LAPUR program consists of two autonomous modules, LAPURX and LAPURW, which are linked by means of an intermediate storage routine. The first module, LAPURX, solves the governing equations for the coolant and the fuel steady state. Map of the core steady state are generated and stored in data files for subsequent utilization by LAPURW. The second module, LAPURW, solves the dynamic equations for the coolant, fuel, and neutron field in the frequency domain. A set of open-loop transfer functions are generated and the stability index (decay ratio), is estimated from the closed loop reactivity to power transfer function. Today, personal computers are cheaper and powerful. With its faster and faster computing ability, we can dispatch PC to calculate the routine work, like the repeating parameter testes. In this paper, we use programming skills and loop concepts on LAPUR DR calculation, in order to saving human power on parameter testing. We expect that this method can provide a simple way to those who concentrate on parametric studies, and get a large mount, more and more reliable data easily.
author2 Shih, Chunkuan
author_facet Shih, Chunkuan
Li, Hsuan-Nien
李宣年
author Li, Hsuan-Nien
李宣年
spellingShingle Li, Hsuan-Nien
李宣年
LAPUR穩定性分析方法論的自動化設計
author_sort Li, Hsuan-Nien
title LAPUR穩定性分析方法論的自動化設計
title_short LAPUR穩定性分析方法論的自動化設計
title_full LAPUR穩定性分析方法論的自動化設計
title_fullStr LAPUR穩定性分析方法論的自動化設計
title_full_unstemmed LAPUR穩定性分析方法論的自動化設計
title_sort lapur穩定性分析方法論的自動化設計
publishDate 2009
url http://ndltd.ncl.edu.tw/handle/91799516243684515542
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