龍門核能電廠全黑事故及大破口冷卻水流失事故分析

A Study on the Station Blackout and Large-Break Loss of Coolant Accident Scenarios for Lung-Men Nuclear Power Plant

黃子恩(Tzu-En Huang)

指導教授 ： 鄧治東

中原大學/工學院/機械工程研究所/碩士(2010年)

https://doi.org/10.6840/cycu201000628

摘要

自從美國三哩島(Three Mile Island)事故發生以來，核能工業界逐漸開始重視核能電廠引起之嚴重事故，並以美國電力研究所(Electric Power Research Institute, EPRI)主導並委託Fauske and Associates, Inc. (FAI)公司開發的嚴重事故分析程式(Modular Accident Analysis Program, MAAP)進行核能安全嚴重事故分析。
MAAP程式最新版本MAAP5雖然已開發完成，但在事故分析上大多仍使用舊版MAAP4.0.4，使用新版MAAP5進行電廠相關分析者不多；有鑑於此，本研究將使用MAAP5進行電廠嚴重事故分析，分析之個案為參照龍門電廠終期安全分析報告所描述之電廠全黑事故SBRC-PF-R-N與單純飼水大破口冷卻水流失事故。
本研究將對此兩事故進行分析並加入緊急操作程序書之救援動作，亦即加入冷卻水注水系統，並延遲其注水時間，進行注水時間之靈敏度分析，藉以探討冷卻水注水時間對爐心之影響，期許能提供電廠對於冷卻水注水策略之相關資訊。

關鍵字

緊急操作程序書 ； MAAP ； 龍門電廠 ； 嚴重核子事故 ； 靈敏度分析 ； 冷卻水注水

並列摘要

Subsequent to the Three Mile Island (TMI) accident, the nuclear industry has paid much attention to severe nuclear accident evaluation, and the evaluation was carried out by using the Modular Accident Analysis Program (MAAP) developed by Fauske & Associates, Inc. (FAI). It is noted that MAAP has been used by the nuclear industry as the tool to determine the accident scenarios under postulated severe accident conditions.
The development of the latest MAAP5 version has been completed and the code was released recently; until recently most of severe nuclear accident analyses have been simulated by MAAP4.0.4 version. Studies presenting the results of simulation by MAAP5 have occurred only recently; therefore, the purpose of this study was to use MAAP5 to simulate the severe accident scenarios in the hope to add the evaluation results to the technical literature.
The following accident scenarios were used as representative cases and were based on the Final Safety Analysis Report (FSAR) of Lung-Men Nuclear Power Plant (LMNPP), and the accident scenarios were SBRC-PF-R-N and LOCA with break in feedwater line, namely, Station Blackout (SBO) and Large Break Loss of Coolant Accident (LOCA).
This study was intended to analyze two representative severe accident scenarios with Emergency Operation Procedures (EOPs) and to discuss the influence of injection delay with AC-Independent Water Addition (ACIWA) and High Pressure Core Flooder (HPCF) on the behaviors of the core, reactor pressure vessel, and hydrogen generation. It was hoped that the strategy of coolant injection could provide useful information for the plant staff in responding to the postulated severe accidents.

並列關鍵字

Severe Accidents ； MAAP ； LMNPP ； Emergency Operation Procedures (EOPs) ； Coolant Injection

參考文獻

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