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題 名 | IIST設施實驗模擬半水位運轉餘熱移除系統失效意外事故=Experimental Investigation of PWR Mid-Loop Operations with Loss of Residual Heat Removal in IIST Facility |
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作 者 | 李堅雄; 劉泰健; 張欽章; 魏元勳; 夏德鈺; | 書刊名 | 核子科學 |
卷 期 | 34:1 1997.02[民86.02] |
頁 次 | 頁23-36 |
分類號 | 449.7 |
關鍵詞 | 半水位運轉; 雙相流; 壓水式核能電廠; Mid-loop operation; Two-phase flow; PWR; |
語 文 | 中文(Chinese) |
中文摘要 | 壓水式核能電廠比例縮小安全測試設施(IIST)執行七種不同狀況下,餘熱移除系統失效之半水位運轉實驗。深入探討爐心功率、可使用環路數目、壓力槽內旁通流量、系統密閉或開口(調壓槽洩壓閥導通或壓力槽頂部洩壓閥導通)等重要參數,對於系統昇壓及爐心祼露之靈敏度。實驗的結果有助於瞭解半水位運轉重要熱流現象發生的機制,以及提供實驗數據,用來發展和驗證半水位運轉熱流安全分析程式。 |
英文摘要 | A series of seven experiments was conducted at the INER Intergral System Test (IIST) facility to investigate the thermal hydraulics of the PWR mid-loop operations with loss of residual heat removal. The sensitivity studies of important parameters closely related to pressurization and core uncover, such as core power, available loops, core bypass flow, closed system or open system (pressurizer venting and pressure vessel venting), are presented in detail. The experimental results are useful not only in the understanding of the mechanisms for the key thermal-hydraulic phenomena but also in assessment and development of the thermal-hydraulic computer codes for the analysis of mid-loop operations. |
本系統中英文摘要資訊取自各篇刊載內容。