本論文使用美國愛德華國家工程實驗室所發展的RELAP5/Mod3分析程式，建立我國第一座核能發電廠－金山核能發電廠的用過燃料池輸入模式。
本研究內容主要包括：(1) 依照美國核管會標準審查方案附的衰變熱功率計算式為基礎，計算核一廠一號機所有退出用過燃料元件產生的衰變熱。對於最新退出的第24和25週期產生的衰變熱，採用退出時在反應爐內最後的發熱功率，當成計算衰變熱的初始功率；(2)將核一廠一號機用過燃料池內擺放最多用過燃料第25週期區域的幾何模型建立出來，並利用結合 (lumped method) 的方法，讓程式計算時更有效率；(3)根據用過燃料元件實際的擺放方式，建立出輻射熱傳導模式；(4)分析反向極限限制流模式 (Counter Current Flow Limitation, CCFL) 和輻射熱傳模式，兩種模式對用過燃料池喪失冷卻事故的影響；(5)在用過燃料池喪失冷卻事故後的不同時間，進行不同灑水量的靈敏度分析。
輸入檔建立完成後，進行穩態計算；建立在有冷卻將用過燃料產生的衰變熱帶走的情況下，用過燃料池內水溫、壓力、與流速的分佈。發生喪失冷卻事故後，燃料池的水溫會漸漸升高而開始沸騰，水位不斷地下降，當用過燃料元件裸露後，護套溫度會非常快速的上升。分析結果顯示，用過燃料池發生喪失冷卻事故後，用過燃料元件裸露的時間為事故後6.57天，而護套溫度達到2200℉ (1200℃) 的時間為8.1天。程式所預測的裸露時間，較以簡單的能量平衡所計算的時間早13.2小時。最早發生燃料裸露的燃料束不是功率密度最高的燃料束。反向極限限制流模式和輻射熱傳模式對模擬的結果影響有限。
模擬結果顯示，用過燃料池喪失冷卻發生事故時，越早進行灑水，越能縮短池水重新覆蓋用過燃料元件的相對時間，灑水量加大越可以有效地降低燃料護套的溫度。

In the present study, a RELAP5/Mod3 input deck for the spent fuel pool of the Chinshan Nuclear Power Station of Taiwan Power Company is developed. Chinshan nuclear power station employs a Boiling Water Reactor (BWR IV) designed by General Electric and Mark I containment. The input deck is used to analyze the loss of cooling event of spent fuel pool.
The work involved in the study includes：(1)Use the ASB-92 formula to calculate decay power of the spent fuels. The spent fules of the latest discharged cycle are calculated in detail. The decay power generated in these spent fuel depends on the final power of the spent fuels during operation. (2) The lumped parameter approach is adopted to model the spent fuel racks within the pool. The rack which contains maxmum numbers of the latest cycle of spent fuels is model in detail. (3) The radiation heat transfer model is built. (4) The impact of counter current flow limit (CCFL) and radation heat transfer model is assessed. (5) Sensitivity studies of the cooling effect of water spray on the heat up of spent fules are performed.
The results indicate that spent fuel is uncovered at 6.75 days after accident takes place and the cladding temperature rises above 2200℉at 8.1 days after accident takes place 8.1 days. The time is about 13.2 hours less that the results predicted using simple energy balance method. The results also show that the impact of CCFL and radiation heat transfer model is marginal.
The results indicate that the earlier take spray action, the shorter time to recover the spent fuel will take.If the capacity of spray is bigger, the cladding temperature will be decreased more effectively.

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