Transient Analysis of ATWS Events for Lungmen by Modified PCTRAN-ABWR Code

碩士 === 國立清華大學 === 核子工程與科學研究所 === 98 === The purpose of this work is to perform an Anticipated Transient Without Scram (ATWS) safety analysis of Lungmen nuclear power plant (LMNPP) in Taiwan. PCTRAN-ABWR is a NPP transient and accident simulation code with high efficiency and convenience. Because PCT...

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Bibliographic Details
Main Authors: Chang, Kailan, 張凱嵐
Other Authors: Shih, Chunkuan
Format: Others
Language:zh-TW
Published: 2010
Online Access:http://ndltd.ncl.edu.tw/handle/38457368353136091059
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Summary:碩士 === 國立清華大學 === 核子工程與科學研究所 === 98 === The purpose of this work is to perform an Anticipated Transient Without Scram (ATWS) safety analysis of Lungmen nuclear power plant (LMNPP) in Taiwan. PCTRAN-ABWR is a NPP transient and accident simulation code with high efficiency and convenience. Because PCTRAN-ABWR only consider mass equation and energy equation, it can simulate a variety of accident and transient conditions with little computer resources. In original version, the logics of ATWS are not enough perfect, therefore this work modified this code and added some new logics of ATWS events into modified PCTRAN-ABWR. This work performed by two parts as show as the following:(1)To improve the analyzed ability, the ATWS logics and set points in PCTRAN-ABWR code is modified including ARI, FMCRD and SLCS, according to Final Safety Analysis Report (FSAR) 15E.6.(2)Two ATWS cases with the following initiating events, Main Steam Isolation Valve Closure and Loss of Offsite Power selected from FSAR 15E.6, were performed to verify the modified PCTRAN-ABWR. These ATWS mitigation benchmarks show PCTRAN-ABWR has a good ability to simulate ATWS events and their mitigation functions of LMNPP design. In addition to the above DBA analyses, this work analyzed three beyond-DBA cases including Main Steam Line Break Loss-of-Coolant Accident (LOCA) combined with ATWS, Feed Water Line Break LOCA combined with ATWS, and High Pressure Core Flooder (HPCF) Line Break LOCA. The defense-in-depth in nuclear power plant could be observed in these transient analyses.