臺灣博碩士論文加值系統

本研究係利用非破壞性加馬能譜量測法，以高純鍺偵檢器測量TRIGA核燃料分裂產物之活性，並運用疊代計算法發展計算程式，以評估並推導核燃料之燃耗值。
文獻顯示，在傳統上一般皆使用長半衰期分裂產物來分析核燃料的燃耗，但在1986年至1990年期間，清華大學另行發展並建立了一套新的燃耗分析方法，利用片狀MTR用過燃料，將其重新置於反應器爐心再照射，而後量測其中堆積之短半衰期分裂產物140La的活性，再推導出燃料之燃耗值。此一方法的特色是可以在欠缺燃料過去照射歷史的情形下，仍推算出燃料之燃耗值。
本研究之目的是希望推廣上述的方法，以短半衰期分裂產物97Zr/97Nb、132I、及140La的活性作為燃耗值指標，分析並推導棒狀TRIGA核燃料之燃耗值。以照射時間、分裂產率、分裂截面、中子通率、以及測得的分裂產物活性為基礎，可建立起疊代計算法，得到用過燃料中所剩餘的235U原子數密度，再由此轉換成燃料燃耗值。然而，由於TRIGA燃料與MTR燃料之間有幾何形狀（前者為棒狀，後者為片狀）和235U濃縮度（前者為20%，後者為93%）的差異，故雖有過去MTR用過燃料燃耗之分析基礎，但是當應用此方法於TRIGA燃料燃耗分析時，除了需要修正燃料內部中子通率及自我屏蔽因子的評估外，另外還必須考慮來自239Pu分裂的影響。本文中運用WIMS計算程式進行TRIGA燃料晶格分析，來修正以上影響因素，並進而建立起TRIGA燃料燃耗量測的新分析方法。
經使用新方法評估TRIGA全新燃料中的235U含量（235U濃縮度已知為20%，即相當的燃耗值為0%），其平均誤差在3%以內。運用此方法評估TRIGA用過燃料燃耗值，其結果與傳統長半衰期分裂產物137Cs活性、134Cs /137Cs活性比、及106Ru/137Cs活性比方法所推導的燃耗結果相比較，兩者顯示具一致性，兩者之平均誤差在5%以內。

封面
摘要
誌謝
目錄
表目錄
圖目錄
第一章 導論
1.1 研究背景
1.2 文獻回顧
1.3 本文概要
第二章 實驗設備與系統
2.1 THOR與TRIGA燃料
2.1.1 THOR
2.1.2 TRIGA燃料
2.2 中子通率量測
2.2.1 中子通率計數系統
2.2.2 中子通率計數系統校正
2.2.3 TRIGA中子通率
2.3 燃耗量測系統
2.3.1 燃耗量測計數系統
2.3.2 燃耗量測系統效率校正
第三章 實驗程序與分析評估
3.1 實驗操作程序
3.1.1 燃料再照射
3.1.2 中子通率計數量測
3.1.3 分裂產物計數量測
3.2 中子通率評估
3.3 分裂產物特性分析
第四章 燃耗量測分析
4.1 TRIGA燃料晶格計算
4.1.1 計算處理流程
4.1.2 NJOY核截面數據處理程式
4.1.3 燃料晶格計算
4.1.4 使用的計算機
4.2
4.3 燃料之空間自我衰減因子
4.4 分裂產物活性評估
第五章 疊代計算法推導燃料燃耗值
5.1 短半衰期分裂產物活性推導耗值
5.1.1 由 Zr/ Nb活性推導燃耗值
5.1.2 由 I活性推導燃耗值
5.1.3 由 La活性推導燃耗值
5.1.4 燃耗值推導方法之驗證
5.1.5 結果
5.2 長半衰期分裂產物活性推導燃耗值
5.2.1 由 Cs活性推導燃耗值
5.2.2 由 Cs/ Cs活性比推導燃耗值
5.2.3 由 Ru/ Cs活性比推導燃耗值
5.2.4 結果
第六章 結果分析與討論
6.1 來自 Pu分裂之影響
6.2 燃耗值推導方法之比較
6.3 誤差分析
6.4 討論
第七章 結論
參考文獻
附錄 A 以 Zr活性計算燃耗值程式
附錄 B 以 Cs活性計算燃耗值程式
附錄 C 以 Ru/ Cs活性比計算燃耗值程式
附錄 D 以 Cs推導F-2-30燃料元件之燃耗值及中子通率
附錄 E 指標分裂產物原子數密度之公式推導

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