核能二廠Mark-III圍阻體熱水流分析模式建立

The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment

彭柏皓(Po-Hao Peng)

指導教授 ： 白寶實 ； 施純寬 ； 陳彥旭

國立清華大學/原子科學院/核子工程與科學研究所/碩士(2011年)

摘要

摘要
冷卻水流失事故(Loss of Coolant Accident, LOCA)為設計基準事故(Design Basis Accidents, DBA)之一，其可能會造成圍阻體系統失效。故本研究之主要工作為針對Mark-III圍阻體進行主蒸汽管路斷管事故與再循環管路斷管事故之分析，確保圍阻體能承受事故發生時所造成之壓力與溫度尖值之衝擊。
本研究採用GOTHIC程式建立短程分析模式與長程分析模式：在短程分析模式中，我們採用核能二廠之終期安全分析報告(Final Safety Analysis Report, FSAR) [1]所提供的沖放質能數據作為邊界條件；在長程分析模式中，則是建立RPV模式與ECCS模式並透過Homogeneous Equilibrium Model臨界流模式計算其沖放質能。此外為求得較為保守之計算，短程分析模式與長程分析模式分別採用不同之假設條件：在短程分析模式中，抑壓池之初始水位高度假設為高水位；在長程分析模式中，抑壓池之初始水位高度則是假設為低水位。最後將GOTHIC程式計算結果與FSAR之數據進行比對分析並探討其合理性。
本研究分析結果與FSAR之數據在時變趨勢上相當吻合，並且事故所造成之溫度與壓力尖值與其設計值均有一段差距，故根據其分析結果可得知，在單一事故之假設下，圍阻體系統之完整性安全無虞。

關鍵字：GOTHIC、馬克三、圍阻體、冷卻水流失事故、設計基準事故

關鍵字

GOTHIC ； 馬克三 ； 圍阻體 ； 冷卻水流失事故 ； 設計基準事故

並列摘要

ABSTRACT
The loss of coolant accident (LOCA) is an important issue of design basis accidents (DBA) because it will cause the failure of containment. This thesis has focused on the investigation of the main steam line break and recirculation line break (Double ended guillotine) for the Mark-III containment to ensure that the containment must withstand the peak values of pressure and temperature loadings as an accident impact occurs.
We have utilized GOTHIC program to establish the short-term and long-term analysis models respectively. For the short-term analysis model, we have adopted the blowdown mass and energy release data offered from final safety analysis report (FSAR) to build up the boundary condition. For the long-term analysis model, we have joined the RPV and ECCS models with the homogeneous equilibrium critical flow model to calculate the value of blowdown rate. Furthermore, given in more confident and crucial, the short-term analysis model and the long-term analysis model of the conditions have been assumed to be different, in which the initial water level of suppression pool is higher for the short-term one but lower for the long-term one. As a result, the simulated data have been compared to the data of FSAR, and we will analysis and specify the reasonableness and corrections of the results.
In conclusions, the given results from this work are consistent with the data of FSAR dependent on time. More importantly, the peak value of the temperature and pressure for this accident is much lower than the designed safe value so the containment will be safe and sound when a single accident event occurs.

Key words：GOTHIC、Mark-III、Containment、LOCA、DBA

並列關鍵字

GOTHIC ； Mark-III ； Containment ； LOCA ； DBA

參考文獻

4. 洪振育，「龍門電廠ABWR圍阻體熱水流分析模式建立」，國立清華大學工程與系統科學研究所，碩士論文，民國99年。

參考文獻

1. Taiwan Power Company, “Final Safety Analysis Report”, Kuosheng Nuclear Power Station Units 1 and 2, Amendment No. 12, December 2001.

2. 劉壁銘，「核四廠圍阻體系統大破口失水事故下之熱流分析」，國立清華大學工程與系統科學研究所，碩士論文，民國91年。

3. 陳彥旭，「核一廠一、二號機再循環管路斷管一次圍阻體壓力與溫度響應計算書」，核能研究所，民國99年。