查詢結果分析
來源資料
頁籤選單縮合
題 名 | 沸水式反應器保護系統測試週期之合理化研究=Analysis of Surveillance Test Interval for Reactor Protection System of a Boiling Water Reactor |
---|---|
作 者 | 李敏; 游琦焜; | 書刊名 | 台電工程月刊 |
卷 期 | 587 1997.07[民86.07] |
頁 次 | 頁105-120 |
分類號 | 449.2 |
關鍵詞 | 測試週期; 核電廠安全; 安全度評估; Surveillance test interval; Nuclear power plant safety; Probabilistic risk assessment; |
語 文 | 中文(Chinese) |
中文摘要 | 本研究利用活態安全度評估模式及架構之故障樹探討核二廠沸水式反應器控制棒 系統之相關運轉規範的適切性。分析工作包括架構液壓控制單元、反應器保護系 統(Reactor Protection System, EPS)、替代揮棒系統之故障樹;及收集故障樹 相關基本事件之一般數據與核二廠之個廠數據以量化控制棒系統失效機率。 故障樹分析驗證了反應器保護系統的高度可靠性,加上替代揮棒系統的後援, 使得急停信號失效機率在放寬測試週期後,對電廠全部的年爐心熔毀機率無明顯 的影響。RPS測試週期的適當放寬,造成RPS不可用度的增加,並不曾明顯增加 電廠的年爐心熔毀機率。測試週期的適當放寬可以減少檢修人員的負擔,降低系 統元件因不必要測試所累積的磨耗,同時可以減少因測試造成之跳機次數。各種 急停信號的測試,週期可由原先的31天(APRM原先為7天)放寬至92天;至於 急停接點的測試,而原先每31天執行一次的手動急停測試改為每7天執行,以減 少因其他測試週期放寬而增加的系統不可用度。 |
英文摘要 | The living probabilistic risk assessment (PSA) model was used to analyze the impact of surveillance test interval (STI) of reactor protection system on the core damage frequency of Kuosheng nuclear power plant which employed a General Electric Designed BWR6 (Boiling Water Reactor) reactor. Fault trees are constructed and plant specific data were collected to quantify the failure probability of the control rod system. The system fault trees constructed included the control rod drive mechanism, the hydraulic control unit (HCU), the reactor protection system (RPS), and the redundant reactivity control system (RRCS). The results of the study showed that the failure probability of RPS will not increase significantly and the core damage frequency was relatively unchanged when the STI of the related components increased. The backup provided by the RRCS reduced the importance of RPS. The increase of STI can reduce the work load of plant staff, the wear out of the related components, and the number of scram caused by human error during the test. It was suggested that the STI of the SCRAM can be extended from 31 days to 92 days. The STI of scram contact point should reduce from 31 days to 7 days to lower the impact of STI changes of scram signal on the overall failure probability of the control system. |
本系統中英文摘要資訊取自各篇刊載內容。