臺灣博碩士論文加值系統

台灣電力公司龍門核能電廠(LMNPP)是以全數位化、分散式控制、多工網路技術建構核能電廠的儀控設施，以微處理器及軟體的技術為基礎設計生產核能電廠內安全、非安全相關系統的數位儀控設施；不過以微處理器及軟體技術為核心的數位儀控設施有不可預測的軟體錯誤與軟體共因失效(Common Cause Failure)的潛在問題存在。 由於軟體錯誤或共因失效問題出現的當下可能會破壞核能電廠安全保護設施的硬體多重性(Redundancy)，將造成核能電廠重大的影響。 因此，多樣性的備選設計及實現方式(Diverse Backup Implementation)是核能儀控設施克服軟體錯誤與軟體共因失效問題的重大方案。 本研究探討以現場可程式邏輯陣列(Field Programmable Gate Array, FPGA)技術實現部份馬鞍山PWR核能電廠、龍門ABWR核能電廠儀控設施的可行性及初步設計。
首先，本研究以FPGA技術實現馬鞍山PWR核能電廠的預期暫態未急停緩和系統致動線路(Anticipated-Transient-Without-Scam Mitigation System and Actuation Circuit, AMSAC)之觀念及初步設計，並在AMSAC電路與驗證電腦(簡化的反應器/電廠系統介面)間設計一個工程模擬介面視窗軟體，提供三迴路FPGA-based AMSAC電路的功能測試環境。
第二，本研究展示一個ABWR飼水控制器的新設計，並與龍門電廠自動化功率調節系統(Automatic Power Regulating system, APR)整合運轉。 新的ABWR飼水控制器採用FPGA技術實現規則化的階層式模糊邏輯控制理論(Rule-based Hierarchical Fuzzy Logic Control Algorithm)，FPGA-based飼水控制器整合於龍門電廠的全功能工程模擬器，並依循龍門電廠自動功率調節的兩條功率/爐心流量圖(Power/Flow Map)軌跡，於APR自動功率調節運轉模式下進行功能驗證與性能評估，並與原ABWR飼水控制器進行性能比較；新設計在暫態反應(Transient Response)及穩態追蹤能力(Steady State Tracking Capability)兩方面都有不錯的表現；模擬的結果顯示，在先進核能電廠自動化運轉及應用上，FPGA-based規則化階層式模糊邏輯控制器是實用的設計方式。
第三，本論文探討以FPGA技術為基礎設計龍門電廠ABWR的四迴路RPS反應器保護系統，此FPAG-based RPS電路整合於龍門電廠全功能工程模擬器進行功能驗證與系統評估；在系統評估時，以龍門電廠的事故腳本或不正常條件加入工程模擬器以便啟動RPS的功能。 模擬的結果顯示，以FPGA技術為基礎設計核能電廠的儀控系統是實現多樣性備選設計的一種實用方式，同時對台灣電力公司其他核能電廠的傳統類比式儀控系統的現代化與更新也是一個容易及方便的設計技術。 由於FPGA電路運轉中無其他軟體的介入，可以降低不可預測的軟體錯誤及軟體共因失效的風險，同時也可以減少核能電廠申請執照時面臨法規對軟體的限制與成本支出。
最後，本研究進行龍門電廠PRA (Probabilistic Risk Assessment)的靈敏度分析，結果顯示RPS結合ARI(Alternative Rod Insertion)系統驅動龍門電廠控制棒的機構對爐心熔毀頻率(Core Damage Frequency, CDF)的計算貢獻很大；本研究的PRA靈敏度分析與RPS的設計科技無關。

The instrumentation and control (I&;C) systems for the Lungmen nuclear power plant are fully digitized based on microprocessor and software technology, and extensively utilize multiplexing networks. That is, undetectable software faults and common cause failures due to software errors may occur, and that will defeat the redundancy of a nuclear power plant (NPP). A diverse backup implementation for the digital I&;C systems is an important means to defense against undetectable software faults. This research is to explore the feasibility and preliminary design of using FPGA-based instrumentation and control systems for nuclear power plants (PWR type Maanshan NPP and ABWR type Lungmen NPP).
First, this research explores a concepture design of using FPGA-based triple-redundant system for Anticipated-Transient-Without-Scam Mitigation System and Actuation Circuit (AMSAC) for Taipower’s Maanshan PWR type NPP. A simulated interface between AMSAC system and simplifed reactor/plant systems is developed to provide a test environment to validate the triple-redundant FPGA-based system.
Second, this paper presents a new feed-water controller under the automatic power regulating system (APR) for Taipower’s Lungmen ABWR type NPP (LMNPP). The new feed-water controller is designed by using a rule-based hierarchical fuzzy logic control algorithm and is implemented by using the modern FPGA technology. The FPGA-based feed-water controller is integrated into the LMNPP’s full-scope engineering simulator with APR system for validation and performance evaluation. Under automatic power maneuvers, two trajectories in the power/flow map have been tested and compared with the origin design. The transient response and the steady state tracking capability are evaluated and showed satisfactory results. The results demonstrate that the FPGA-based hierarchical fuzzy logic controller is a practical approach for automatic power operations in advanced nuclear power plant applications.
Third, this paper presents the system assessment of a quad-redundant RPS system design for Taipower’s Lungmen ABWR type NPP by utilizing FPGA technology. The FPGA-based RPS system has been assessed by using the LMNPP’s full-scope engineering simulator. Accident scenarios and abnormal conditions are inserted into the engineering simulator in order to activate the function of the FPGA-based RPS. The assessment results demonstrate that the FPGA-based nuclear instrumentation and control system is a practical approach to implement a diverse backup for nuclear power plant applications and can easily be used for the modernization of Taipower’s nuclear power plant analog systems. The software-free FPGA-based system may reduce the safety risk of undetectable software faults and common cause failures, and also minimize the regulatory licensing efforts and cost.
Final, the sensitivity study of probabilistic risk assessment (PRA) shows that RPS combined with ARI (Alternative Rod Insertion) contributes significant influence on the core damage frequency (CDF) calculation of LMNPP. The PRA sensitivity study is independent of the RPS technology.

中文摘要 i
ABSTRACT iii
致謝 v
目 錄 vi
表 目 錄 x
圖 目 錄 xi
第一章 前言 1
1.1 核能電廠數位儀控之相關法規與問題 3
1.1.1核能電廠數位儀控之相關法規 3
1.1.2 微處理器軟體潛在失效之複雜性 5
1.1.3 核能電廠類比式儀控設施老化、更新、延壽 6
1.2 研究目的與範圍 7
第二章 文獻回顧與探討 9
2.1 FPGA技術應用於核能領域之文獻 9
2.2 美國Wolf Creek核能電廠與ALS系統平台 14
2.3 美國Oconee核能電廠 22
2.4 中國大陸廣東省嶺澳核能電廠 Phase II 23
2.5 可程式化邏輯家族 25
2.6 FPGA發展系統資料蒐集與分析 27
2.6.1 Actel's SmartFusion智慧型混合訊號FPGA晶片 30
2.6.2 SmartFusion晶片設計流 34
2.7 馬鞍山核能電廠AMSAC系統 37
2.8 ABWR飼水控制系統 44
2.9 模糊邏輯 45
2.10 龍門電廠APR自動功率調節系統 47
2.10.1 APR的設計準則 47
2.10.2 APR的系統運作 49
2.11 龍門核能電廠RPS反應器保護系統 53
2.12 龍門電廠全功能模擬器與3Key Master模擬軟體平台 58
2.13 WinNUPRA可靠度分析軟體 63
第三章 設計原理與研究步驟 65
3.1 建構龍門電廠之工程型模擬器 66
3.2 以FPGA建置馬鞍山電廠AMSAC系統 69
3.2.1 FPGA-Based AMSAC系統設計、功能驗證架構 70
3.2.2 FPGA-Based AMSAC系統電路設計 71
3.3 以FPGA階層式結構模糊邏輯建置龍門電廠飼水控制系統 74
3.3.1 Hierarchical FLC的設計原理 76
3.3.2 階層式結構FLC邏輯電路的硬體設計 80
3.3.3 FPGA邏輯電路與模擬器系統評估的軟體介面 81
3.4 以FPGA建置龍門電廠反應器保護系統 82
3.4.1通用FPGA系統平台之選擇 82
3.4.2 FPGA-Based RPS電路板系統設計 83
3.4.3 FPGA-Based RPS驗證評估架構設計 84
3.4.4 FPGA邏輯電路設計 86
3.4.5 FPGA-Based RPS邏輯電路的資料流程 88
3.4.6 FPGA邏輯電路與模擬器系統評估的軟體介面 90
第四章 研究結果與討論 92
4.1馬鞍山電廠FPGA-based AMSAC系統功能驗證 92
4.1.1 FPGA-based AMSAC系統電路功能現階段功能驗證 92
4.1.2 FPGA電路未來Close-Loop功能驗證之建議 94
4.2 龍門電廠FPGA階層式結構模糊邏輯飼水控制系統功能驗證 96
4.2.1 FPGA電路離線功能驗證 96
4.2.2 FPGA電路於模擬器上系統效能比較 (Trajectory A) 96
4.2.3 FPGA電路於模擬器上系統效能比較 (Trajectory B) 99
4.3 龍門電廠FPGA-based RPS系統功能驗證 103
4.3.1 FPGA電路離線功能驗證 104
4.3.2 Steam Line B Breaks inside Dry-Well事故系統評估 107
4.3.3 Feed-Water Line A Double End Breaks Inside Containment事故評估 109
4.3.4 Simultaneous Closure of All 8 MSIVs事故系統評估 111
4.3.5 Loss of In-House AC Power (EDGS Start) 事故系統評估 113
4.4 龍門核能電廠RPS系統之PRA模式靈敏度分析 115
4.4.1 龍門核能電廠之PRA模式 115
4.4.2 龍門核能電廠RPS系統之PRA模式靈敏度分析結果 118
第五章 結論與建議 120
5.1 結論 120
5.2 建議與討論 122
參考文獻 126

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