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| 題名 | IIST設施實驗研究小破口冷卻水流失事故爐心冷卻不足之救援措施=Experimental Investigation of Accident Management for Small Break Loss-of-Coolant Accident Resulting in Inadequate Core Cooling at the IIST Facility |
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| 作者 | 張建業; 李堅雄; 劉泰健; Chang, C. Y.; Lee, C. H.; Liu, T. J.; |
| 期刊 | 核子科學 |
| 出版日期 | 19980400 |
| 卷期 | 35:2 1998.04[民87.04] |
| 頁次 | 頁91-102 |
| 分類號 | 449.2 |
| 語文 | chi |
| 關鍵詞 | 小破口冷卻水流失意外事故; 緊急運轉程序書; 壓水式核能電廠; Small break loss-of-coolant accident; Emergency operating procedure; PWR; |
| 中文摘要 | 核能研究所壓水式反應器比例縮小安全測試設施中，假設高壓注水系統完全失效 之情況下，進行一系列冷管小破口（ 0.2% ∼ 2% ）及調壓槽釋壓閥卡開冷卻水流失事故， 造成爐心冷卻不足採取救援措施之實施，本文深入探討不同破口位置所造成特殊熱流的現象 ，對於採取救援措施時機之影響。 研究結果發現：（ 1 ）調壓槽釋壓閥卡開事故時，當爐 心內燃料棒裸露昇溫至 520K 後，採取二次側洩壓補水救援措施，能瞬間使調壓槽內冷卻水 回流注滿爐心，隨著一次側系統壓力下降，蓄壓槽及低壓注水系統的冷卻水先後注入爐心， 可維持其長期冷卻； （ 2 ）冷管小破口冷卻水流失事故時，當爐心內燃料棒裸露昇溫後， 採取二次側洩壓補水救援措施，由於蓄壓槽冷卻水部份會經由冷管破口處流出系統，及部份 冷卻水進入壓力槽降流區接觸到熱壁產生沸騰現象。 因此燃料棒溫度會繼續昇至 900K，而 使得在實驗停止前，蓄壓槽冷卻水仍未注滿爐心；（ 3 ） IIST 及美國 Semiscale Mod-2C 之實驗結果均顯示，當冷管小破口造成壓力槽水位（ collapsed liquid level ）下降至燃 料棒頂部時，就採取緊急救援措施，可有效維持爐心長期冷卻。 |
| 英文摘要 | A series of experiments was conducted at the INER Integral System Test (IIST) facility to investigate the accident management procedures for the inadequate core cooling, resulting from the cold leg and PORV stuck open small break loss-of-coolant accidents (SBLOCA) with the total failure of high pressure injection (HPI) system. The cold leg break areas are ranging from 0.2 to 2% of the scaled cold leg flow area. The key thermalhydraulic responses corresponding to the variations of break locations and break sizes during the inadequate core cooling with the accident management are explored in the present paper. Experimental results showed that (1) In the PORV stuck open experiment, the accident management of the steam generator (SG) secondary bleed-and-feed operation was initiated when the core cladding began to heat up. A rapid secondany depressurization will increase the heat removal from primary to secondary sides as well as water in the pressurizer instantaneously flowing into the core resulting from the flooding phenomenon can not be maintained in the surge line. The continued primary depressuration will eventually cause the initiation of accumulators (ACC) and low pressure injection (LPI) to maintain the long term core colling; (2) In the cold leg SBLOCA experiments, the SG secondary bleed-and-feed operation was initiated when the core cladding began to heat up. As primary depressurization will cause ACC injection, the water from the ACC was partly flowed throughout the break nozzle into the catch tank and partly vaporized due to downcomer hot wall effect. Therefore, the temperature of core cladding continously increased to the trip setpoint of 900 K before core recovery by ACC injection flow; (3) The cold leg SBLOCA experiments conducted at both IISt and SEMISCALE MOD-2C facilities show that the operation of steam generator secondary bleed-and-feed when the pressure vessel collapsed liquid level has dropped to the top of core is a valid accident management procedure to maintain the long term core cooling. |
本系統之摘要資訊系依該期刊論文摘要之資訊為主。