簡易檢索 / 詳目顯示

研究生: 林冠源
Lin, Kuan Yuan
論文名稱: 國聖電廠類福島全黑事故之模擬與分析
Simulation and Analysis of Kuosheng NPP Station Blackout Based on Fukushima Accident
指導教授: 施純寬
王仲容
口試委員: 王仲容
林浩慈
學位類別: 碩士
Master
系所名稱: 原子科學院 - 核子工程與科學研究所
Nuclear Engineering and Science
論文出版年: 2012
畢業學年度: 100
語文別: 中文
論文頁數: 77
中文關鍵詞: 福島事件電廠全黑TRACE燃料護套尖峰溫度生水
外文關鍵詞: Fukushima Accident, Station Blackout, TRACE, PCT, Alternate Water System
相關次數: 點閱:2下載:0
分享至:
查詢本校圖書館目錄 查詢臺灣博碩士論文知識加值系統 勘誤回報
  • 本論文主要模擬國聖電廠發生類似福島事件之事故,透過不同條件的假設,評估核電廠安全系統的應付能力,並提供事故發生時動作決策時機上的參考。情境模擬以電廠全黑為基礎,並假設所有緊急爐心冷卻系統皆失效,於爐心水位降至三個不同高度(1)TAF,(2)爐心裸露1/3高度,(3)BAF時啟動自動釋壓系統洩壓,生水於爐心壓力降至低壓0.779MPa時注入,全部分析以燃料護套溫度(PCT)不超過明顯開始氧化之限值1088.706K為最大前提,以最小流量、時間兩種角度去評估分析結果。本研究所使用之TRACE程式為美國核管會最新發展的一套熱水流安全分析程式,可廣泛的應用於輕水式核能電廠的各種暫態與冷卻水流失事故的分析。為了提升核二廠TRACE模式之可信度,本論文使用100%功率負載棄載啟動測試進行驗證並得到良好結果。而本論文之主要分析結果顯示,國聖電廠既有之生水系統設計足以應付類似福島之事故,且在充足的設計流量下,延長了動作決策時機的範圍,能有效地緩和此類事故在時間上的急迫性。


    In this research, the management ability of Kuosheng Nuclear Power Plant’s safety system is evaluated in different conditions through simulates a situation similar to Fukushima accident. In addition, the decision-making strategies during such severe accident are provided in this research as well. The situation simulation is based on SBO and assumes that all the Emergency Core Cooling Systems fail. The Automatic Depressurization System is activated under the conditions of three different core water levels (1) TAF, (2) one-third of fuel rods uncovered, (3) BAF. When the core vessel reaches the low pressure of 0.779 MPa, the alternate water system is activated in sequent. All the analyses presuppose that the peak cladding temperature (PCT) does not exceed the limit of 1088.706K and the analysis results are evaluated in two considerations which are minimum alternate water flow and time scale. The analysis code used in this research, TRACE (TRAC/RELAP Advanced Computational Engine), is a modernized thermal-hydraulic code developed by the U.S NRC. It can perform best-estimate analyses of loss of coolant accidents (LOCAs), operational transients, and other accident scenarios in light-water reactors (LWRs). In order to enhance the reliability of Kuosheng TRACE model, 100% power load rejection start up test is chosen in this research and the verified results are in agreement on test data. Furthermore, the main analysis result of this research indicates that the alternate water system installed in Kuosheng NPP can cope with a similar accident as severe as Fukushima event. Besides, the design of sufficient flow rate extends the time needed for decision-making and effectively mitigates the urgency when such accident occurs.

    摘要 i ABSTRACT ii 致謝 iv 目錄 v 表目錄 viii 圖目錄 ix 第一章 前言 1 1.1 福島事件回顧 1 1.2 研究目的與方法 2 1.3 分析程式介紹 3 1.3.1 TRACE程式介紹 3 1.3.2 SNAP程式介紹 4 1.3.3 AptPlot程式介紹 6 第二章 文獻回顧 13 2.1 電廠全黑 13 2.2 台電機組斷然處置程序 15 2.3 TRACE程式文獻回顧 17 第三章 核二廠TRACE模式建立與驗證 20 3.1 TRACE基本模式 20 3.2 重要系統模擬 23 3.2.1 爐心隔離冷卻系統(RCIC) 23 3.2.1.1 系統概述 23 3.2.1.2 TRACE模式 23 3.2.2 自動釋壓系統(ADS) 24 3.2.2.1 系統概述 24 3.2.2.2 TRACE模式 25 3.2.3消防水系統(生水供給) 25 3.2.3.1 系統描述 25 3.2.3.2 TRACE模式 25 3.3 動畫模式建立 26 3.4 核二廠TRACE 分析模式驗證 27 3.4.1 核二廠100%功率負載棄載測試 27 3.4.1.1 電廠測試說明 27 3.4.1.2 分析模擬 27 3.4.1.3 分析結果 27 3.4.1.4 靈敏度分析 28 第四章 核二廠類福島全黑事故模擬分析 57 4.1 模擬說明 57 4.2 初始狀態與分析假設 57 4.3 分析結果 58 4.3.1 案例一分析結果 58 4.3.2 案例二分析結果 59 4.3.3 案例三分析結果 59 第五章 結論與建議 73 5.1 結論 73 5.2 建議 74 參考文獻 75

    [1] U.S. Nuclear Regulatory Commission, Applied Programming Technology, Inc., Symbolic Nuclear Analysis Package(SNAP) User’s Manual, 2007
    [2] U. S. Nuclear Regulatory Commission, “ Title 10, Code of Federal Regulations”, 2012
    [3] U. S. Nuclear Regulatory Commission, “Reactor Safety Study: An Assessment of Accident Risks in U.S Commercial Nuclear Power Plants”, WASH-1400, 1975
    [4] U. S. Nuclear Regulatory Commission, “REGULATORY GUIDE 1.155, STATION BLACKOUT”, REGULATORY GUIDE, 1988
    [5] Nuclear Management and Resources Council, “Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors”, NUMARC-8700, 1987
    [6] U.S. Nuclear Regulatory Commission, “THE NEAR-TERM TASK FORCE REVIEW OF INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT”, 2011
    [7] U. S. Nuclear Regulatory Commission, “Proposed Rules”, Federal Register, Vol. 77, No. 54, 2012
    [8] 台灣電力公司,「第二核能發電廠營運程序書1451」,版次24,中華民國一百零一年六月
    [9] 李京翰,「核一廠TRACE模式的建立與驗證」,國立清華大學核子工程與科學研究所,碩士論文,中華民國九十八年
    [10] 陳龍文,「核二廠TRACE模式的建立與驗證」,國立清華大學核子工程與科學研究所,碩士論文,中華民國九十八年七月
    [11] Jong-Rong Wang, et. al., “TRACE modeling and its verification using Maanshan PWR start-up tests”, Annals of Nuclear Energy, 36, 2009, 527-536.
    [12] 楊書明,「台電核四廠TRACE安全分析模式建立與穩態分析」,國立清華大學核子工程與科學研究所,碩士論文,中華民國九十七年八月
    [13] Jung-Hua Yang, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shiha, “LBLOCA analysis for the Maanshan PWR nuclear power plant using TRACE”, Nuclear Engineering and Design,vol.14, 2012, 292-297.
    [14] Jong-Rong Wang, et. al., “The Turbine Trip without Bypass Analysis for Lungmen ABWR Using TRACE/PARCS”, 2nd International Conference on Advances in Energy Engineering(ICAEE), 2011.
    [15] 陳淑娟,「TRACE程式之中子動力模式研究與應用」,國立清華大學核子工程與科學研究所,碩士論文,中華民國九十九年七月
    [16] Chin-Jang Chang, et. al., “IIST small break LOCA experiments with passive core cooling injection”, Nuclear Engineering and Design, 236, 2006, 19-34.
    [17] Byoung Uhn Bae et. al. “Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA”, Nuclear Engineering and Design, 239, 2008, 2197-2205.
    [18] U.S. Nuclear Regulatory Commission, “TRACE V5.0 USER’S MANUAL”, 2010
    [19] 簡弘欽,「核二廠RETRAN模式設計檔案」,INER-A1048H,核能研究所,中華民國九十五年八月
    [20] U.S. Nuclear Regulatory Commission, “TRACE V5.0 THEORY MANUAL”, 2010
    [21] 台灣電力公司第二核能發電廠,「核二廠訓練教材」
    [22] Kuan Yuan Lin, “Verification of the Kuosheng BWR/6 TRACE Model with Load Rejection Startup Test”, ASME 2012 V&V.

    無法下載圖示 全文公開日期 本全文未授權公開 (校內網路)
    全文公開日期 本全文未授權公開 (校外網路)

    QR CODE