查詢結果分析
來源資料
頁籤選單縮合
題 名 | 核研所IIST設施模擬蒸汽產生器U型管破裂意外事故之實驗研究=Experimental Study on Steam Generator Tube Rupture in Iner Integral System Test Facility |
---|---|
作 者 | 劉泰健; 李堅雄; 張欽章; 張建業; | 書刊名 | 核子科學 |
卷 期 | 34:2 1997.04[民86.04] |
頁 次 | 頁90-101 |
分類號 | 449.7 |
關鍵詞 | 蒸汽產生器U型管破裂; 事故處理; 核能安全; SGTR; Accident management; Reactor safety; |
語 文 | 中文(Chinese) |
中文摘要 | 蒸汽產生器發生單根與多根U型管破裂事故(SGTR)並採取救援措施的實驗研究,已在核研所的『核三廠比例縮小測試設試』(IIST)中進行模擬,破管的尺寸是依據核三廠一支、二支與六支U型管完全斷裂(double-ended broken tubes)的破口流截面積依體積比例縮小原理訂定。本研究主要目的在(1)探討 SGTR 過程中的主要熱流現象以及這些現象發生的機制;(2)驗證電廠救援措施限制一次側與二次側之間洩漏的有效性;以及(3)評估斷管數目對事故之嚴重性;並以實驗數據作為日後驗證電廠大型分析程式 RELAPS5準確性之參考。實驗結果顯示:目前使用的SGTR救援措施足以達到降低輻射外洩與爐心充分冷卻的功能,對於較多破管的事故則必需及早採取隔離受損蒸汽產生器(FSG)之動作。另外,為降低FSG滿溢造成的風險,建議在執行一次側冷卻與降壓過程之前,FSG先作洩水動作以降低其液位。 |
英文摘要 | The thermal-hydraulic phenomena of steam generator tube rupture (SGTR) incidents have been investigated experimentally at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility. The single and multiple SGTR senarios assume the double-ended broken of one-two-and six-steam generator U-tubes on the Maanshan nuclear power station and follow the related emergency operating procedures (EOP) of the reference plant. The objectives of this study are to (i) enhance the understanding of the thermal-hydraulic phenomena; (ii) verify the adequacy of the associated EOP in terminating the primary-to-secondary leakage; and (iii) assess the influence of the number of ruptured tubes on the severity of the incident. The data are further used to assess the accuracy of the RELAP5 code. Through this study, it is found that the current EOP works satisfactorily to terminate the break flow and maintain adequate corecooling. For multi-tubes reputure events, operator action demands substantial early in FSG isolation. In order to minimize the risk of overfilling, it is suggested to drain down the water level in FSG prior to implement RCS cooldown and depressurization process. |
本系統中英文摘要資訊取自各篇刊載內容。