本論文致力於研究耦合運轉參數對燃耗信用（burnup credit，簡稱 BUC）之臨界安全計算的影響。BUC 可改善用過核子燃料貯存設施的單位容量，具有提升經濟價值、減少風險的優點。擬針對三種反應器類型進行研析：沸水式（Boiling Water Reactor，簡稱 BWR）、壓水式（Pressurized Water Reactor，簡稱 PWR），以及高溫氣冷式（High Temperature Gas-cooled Reactor，HTGR）。在計算上，使用 SCALE6.1.3 與 MCNP6.1 程式，並搭配使用 ENDF/B-VII 的中子截面資料庫。各反應器分別建立兩種模型，以用於進行燃耗與臨界安全計算。基本上，隨著運轉參數的相異，造成易裂材料（fissile material）的消耗速率與中子毒物（如分裂產物或部分錒系元素）的產生速率改變，進而使中子增殖因數（effective multiplication factor，簡稱 keff）也將隨之改變，導致反應度偏移（reactivity deviation，簡稱 ∆k）。在此，茲將單項運轉參數與同時考量多項運轉參數對 keff 的影響，分別稱為單一效應（single effect）與複合效應（compound effect），藉以探討各運轉參數之間的耦合關係（coupling dependence）。又複合效應 ∆k 常非單一效應 ∆k 的線性相加，將直接影響臨界安全評估的準確度。因此，本論文擬將各反應器中最重要的運轉參數，進行複合效應的深入探討，並以各效應對中子能譜之影響，瞭解造成效應背後的因由與機制。最後，將總結各複合效應的機制與重要性，以利未來相關研究亦或核能工業參考及使用。

This study aims to investigate the influence of coupling dependence between operating parameters on the burnup credit criticality safety analysis for PWR, BWR, and HTGR spent nuclear fuels. Burnup credit is of vital importance in the criticality safety analysis due to the fact that it can improve the capacity of storage system and subsequently reduce the cost and the risk of storage system. All the calculations were carried out using SCALE6.1.3 and MCNP6.1 Monte-Carlo simulation codes associated with ENDF/B-VII neutron cross section data libraries. In each type of reactors, two geometrical models were established in order to implement the depletion calculations and criticality calculations. In general, the change of operating parameters will induce a reactivity deviation (∆k) due to the variations in the depletion rates of fissile materials as well as the production rates of plutonium, fission products, or other actinides. In convenience, this study defined the effects of simultaneous variations in one and multiple operating parameters on the effective multiplication factor (keff) as the so-called single and compound effects, respectively. Notably, ∆k resulting from compound effects is not always a simple summation of ∆k’s resulting from the associated single effects. This phenomenon may influence the precise assessment of burnup credit to some extent. Furthermore, this study investigated the influences not only on the magnitudes of ∆k’s but also the neutron energy spectrum due to either single or compound effects. The mechanisms causing each single and compound effect were studied in depth as well. Finally, this study concluded the importance of the compound effects in nuclear spent fuel storage for future research or nuclear industrial applications.

摘要 i
Abstract ii
誌謝 iii
目錄 iv
表目錄 vi
圖目錄 ix
第一章、 前言 - 1 -
第二章、 文獻回顧 - 3 -
2.1 PWR相關 之 BUC研究 - 3 -
2.2 BWR 相關之 BUC研究 - 10 -
2.2.1 反應度尖峰相關研究 - 10 -
2.2.2 不含釓之 BWR 用過燃料束相關研究 - 13 -
2.3 其它與用過核子燃料之臨界安全分析相關研究 - 19 -
2.3.1. 模擬計算的偏差與不準度 - 19 -
2.3.2. 用過燃料裝載錯誤與偏心裝載 - 24 -
2.3.3. RBMK 之 BUC 研究 - 26 -
2.4 研究動機 - 28 -
第三章、 計算程式介紹與模型建立 - 29 -
3.1 計算程式介紹 - 29 -
3.2 模型建立 - 34 -
3.2.1 用於 BUC 計算之 BWR 模型 - 34 -
3.2.2 用於 BUC 計算之 PWR 模型 - 51 -
3.2.3 用於 BUC 計算之 HTGR 模型 - 58 -
第四章、 耦合運轉參數於 BWR 用過核子燃料之 BUC 影響 - 61 -
第五章、 耦合運轉參數於 PWR 用過核子燃料之 BUC 影響 - 84 -
第六章、 耦合運轉參數於 HTGR 用過核子燃料之 BUC 影響 - 107 -
第七章、 結論與未來建議 - 123 -
7.1. 結論 - 123 -
7.2. 未來建議 - 125 -
參考文獻 - 126 -
附錄 - 132 -

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