本研究主要目的為利用MELCOR2.2/SNAP探討核一廠除役階段之用過燃料池處於電廠全黑假設事故(Station Blackout, SBO)且發生喪失冷卻水假設事故 (Loss Of Coolant Accident, LOCA)狀況下，鋯合金護套之溫升現象。針對燃料鋯合金護套之氧化關鍵變數因子(如不同氧化模型、不同蒸氣分壓環境與不同氧氣濃度環境)下鋯合金護套的溫升現象進行靈敏度解析，最後選擇溫升最快(保守)之條件 ; 再者，分析目前我國核一廠除役階段一號機用過燃料池是否符合美國核能管制委員會(United States Nuclear Regulatory Commission, U.S. NRC)於2013年發布之SECY-99-168，探討緊急計畫(Emergency Planning, EP)解除或變更條件 : 完全失水下，必須確保鋯合金護套由30°C溫升至900°C有超過10小時之時間餘裕。
本研究成功以MELCOR2.2建立核一廠除役階段用過燃料池MELCOR模式與動畫模式。核一廠一號機停機已近五年，用過燃料池之燃料冷卻時間已達5年以上，依據MELCOR計算結果顯示，不管使用瑞士保羅謝爾研究所開發之Zircaloy-4氧化模型或美國桑迪亞實驗室開發之Zircaloy氧化模型分析，核一廠一號機用過燃料池均符合美國核能管制委員會於2013年發布之SECY-99-168 [1]，探討緊急計畫(Emergency Planning, EP)解除或變更之一條件。

The main purpose of this study is to use MELCOR2.2/SNAP to discuss the long-term loss of AC and DC power (Station Blackout, SBO) and the loss of coolant accident (LOCA) in the decommissioning spent fuel pool of Chinshan Nuclear Power Plant (CSNPP) under the condition of temperature rise of zirconium alloy claddings. Sensitivity analysis of the temperature rise phenomenon of the zirconium alloy claddings under the key oxidation factors of the fuel zirconium alloy claddings (different oxidation models, different vapor partial pressure environments and different oxygen concentration environments), and finally select the condition with the fastest temperature rise (conservative) ; In addition, to analyze whether the current CSNPP in Taiwan is in compliance with SECY-99-168 issued by the United States Nuclear Regulatory Commission (U.S. NRC) in 2013, to discuss Emergency Planning (EP) release or change the conditions: If the water is completely lost, it must be ensured that the zirconium alloy cladding has a temperature rise from 30°C to 900°C for more than 10 hours.
This study successfully used MELCOR2.2 to establish the MELCOR model and animation model of the spent fuel pool in the decommissioning stage of the CSNPP.
CSNPP has been shut down for nearly five years, and the fuel cooling time of the used fuel pool has been more than 5 years. Regardless of the Zircaloy-4 oxidation model developed by the Paul Scherer Institute in Switzerland or the Zircaloy oxidation model analysis developed by Sandia Laboratories in the United States, the MELCOR calculation results show that the spent fuel pool of CSNPP complies with the SECY-99-168 issued in 2013 discussed one of the conditions for the cancellation or change of emergency planning (EP).

摘要 i
ABSTRACT ii
致謝 iii
目錄 iv
表目錄 vii
圖目錄 ix
縮寫表 xiii
符號表 xv
第一章 緒論 1
1.1 前言 1
1.2 研究方法與目的 3
1.3 論文架構與模擬案例簡介 5
1.4 金山電廠介紹 5
第二章 研究背景與文獻回顧 7
2.1 用過燃料池鋯合金火災研析文獻 7
2.1.1 鋯合金氧化(Zircaloy oxidation) 10
2.1.2 NUREG/CR-6846, "Air Oxidation Kinetics for Zr-Based Alloys" [33] 11
2.2 探討緊急計畫解除或變更之一條件文獻回顧 15
2.2.1 SECY-99-168, "IMPROVING DECOMMISSIONING REGULATIONS FOR NUCLEAR POWER PLANTS" [1] 15
2.2.2 RES/DSA/FSCB 2016-03, "Spent Fuel Assembly Heat up Calculations in Support of Task 2 of User Need NSIR-2015-001" [6] 17
第三章 MELCOR嚴重事故分析程式 22
3.1 MELCOR分析用過燃料池之應用 28
3.1.1 鋯合金護套氧化熱(Oxidation Heat)與突偏氧化反應(Breakaway Oxidation) 28
3.1.2 護套膨脹與破裂(Ballooning) 31
3.1.3 鋯合金護套熔融及液化(Melting and Liquefaction) 32
3.1.4 鋯合金護套與燃料之位移及熔渣生成(Candling and Debris) 33
3.1.5 用過燃料池的熱傳模式(Heat Transfer Modeling within Spent Fuel Pool and to Surrounding Walls) 34
3.2 國際間利用MELCOR分析用過燃料池與實驗之驗證 35
3.3 國內核一廠用過燃料池MELCOR與CFD、TRACE、MAAP5平行驗證 37
3.4 SNAP圖形介面化程式 42
3.4.1 SNAP動畫模式建立與應用 43
第四章 核一廠除役階段用過燃料池模式建立 45
4.1 核一廠用過燃料池簡介 45
4.2 MELCOR模式建立 48
4.2.1 COR/CV/FL Package Modeling 48
4.2.2 瑞士保羅謝爾研究所開發之Zircaloy-4氧化模型(PSI Oxidation Model) 53
4.3 衰變熱功率模式建立 55
4.4 燃料軸向功率分布 58
4.5 MELCOR模式驗證 59
4.5.1 用過核子燃料池水溫變化 60
4.5.2 用過核子燃料池水位變化 60
4.5.3 計算與分析結果 61
第五章 長期失電(SBO)與完全失水(LOCA)案例假設與分析結果 65
5.1 瑞士保羅謝爾研究所開發之Zircaloy-4氧化模型(PSI Oxidation Model)之不同鋯合金氧化模型分析 65
5.1.1 不同"蒸氣"氧化模型(Difference Steam Oxidation Model)分析結果 67
5.1.2 不同"氧氣"氧化模型(Difference Oxygen Oxidation Model)分析結果 71
5.1.3 不同"空氣"氧化模型(Difference Air Oxidation Model)分析結果 75
5.2 不同氧氣濃度、蒸氣分壓之溫升影響分析 79
5.2.1 美國桑迪亞實驗室開發之Zircaloy氧化模型分析結果 80
5.2.2 瑞士保羅謝爾研究所開發之Zircaloy-4氧化模型分析結果 86
5.3 緊急計畫解除或變更之一條件分析 92
5.3.1 美國桑迪亞實驗室開發之Zircaloy氧化模型分析結果 93
5.3.2 瑞士保羅謝爾研究所開發之Zircaloy-4氧化模型分析結果 98
第六章 結論與未來建議 101
6.1 結論 101
6.2 未來建議 105
參考文獻 106

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