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題 名 | IIST and Bethsy Counterpart Tests on PWR Total Loss-of-feedwater Transient=壓水式核電廠完全喪失飼水暫態--IIST與BETHSY之比對實驗 |
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作 者 | 劉泰健; | 書刊名 | 核子科學 |
卷 期 | 36:5 1999.10[民88.10] |
頁 次 | 頁316-326 |
分類號 | 449.7 |
關鍵詞 | 壓水式核電廠; 完全喪失飼水暫態; Counterpart test; Loss-of-feedwater; Accident management; |
語 文 | 英文(English) |
英文摘要 | The thermal-hydraulic phenomena of loss-of-feed-water (LOFW) incidents in pressurized water reactor (PWR) have been investigated experimentally at the Institute of Nuclear Energy Research (INER) Integral System Test (HST) facility. To understand whether the physical phenomena observed in the full-height, full-pressure (FHFP) facility during a LOFW transient can be simulated in the reduced-height, reduced-pressure (RHRP) IIST facility, two counterpart tests based on the same scenarios as those of the BETHSY tests were performed. These two tests differ mainly at the initiation of the bleed-and-feed process in order to examine the effectiveness of recovery measures on the conditions of early and late power-operated relief valve open. The present study examines the occurrence of key thermal-hydraulic phenomena as well as their possible distortions. Results of the IIST facility and BETHSY tests showed the common thermal-hydraulic behavior of some key parameters, such as the system pressure, primary coolant inventory, pressurizer level, void fraction in the hot leg, and the discharge mass evolution. The chronological events studied in the RHRP IIST facility are also consistent (in most cases) with those studied in the FHFP BETHSY. |
本系統中英文摘要資訊取自各篇刊載內容。