核二廠及核三廠暫態事件評估與驗證之研究

中文摘要本論文係以RELAP5-3D程式模擬核二廠68﹪功率再循環水跳脫以及核三廠全功率飼水跳脫的暫態事故，觀察此兩個案之模擬結果，驗證RELAP5-3D分析程式是否能適切地分析電廠運轉暫態。核二廠RELAP5-3D輸入模式建立，係以核二廠RELAP5-YA模式中之數值為基礎，進而校驗其正確性；並記錄核二廠RELAP5-3D模式之各項輸入數據之計算根據與計算來源，內容分為四部分，第一部分為Volumes，第二部分為Junctions，第三部分為Heat Structures，第四部分為Control Systems。核三廠RELAP5-3D輸入模式建立，係以原有RELAP-MOD3的核三廠輸入模式轉換及重新核對驗算而來。在核三廠輸入模式中，實際電廠的重要控制系統均已模擬，計有(1)調節一次側壓力的調壓槽加熱器與噴灑閥控制系統；(2)蒸汽產生器水位三元飼水控制系統；(3)蒸汽排放系統；(4)超溫差溫及超載差溫跳脫保護系統；(5)其他跳脫保護系統等。整體而言，本研究藉RELAP5-3D的最佳化分析能力，對兩核能電廠的暫態事件進行模擬，模擬結果顯示，程式運跑的初始值與電廠記錄值大都十分接近(誤差低於1﹪)，所得之重要參數與時變的關係圖，與電廠資料的紀錄值的趨勢係屬一致。

關鍵字

核三廠；核二廠；暫態事件

並列摘要

Abstract This study used the RELAP5-3D code to simulate the transient event of the Second Nuclear Power Station at 68% rated power and with recirculation pump trip (RPT) and the transient event of the Third Nuclear Power Station with feedwater pump trip. The analytical results obtained from these two cases can indicate whether the RELAP5-3D code can adequately validate the operational transients of the nuclear plants under study. The setting-up of the input data file for RELAP5-3D of the Second Nuclear Power Station was based on the data file of the RELAP5-YA code for the same plant. In addition, verifications of the numbers used in the file were carried out to ensure its adequacy. Furthermore, the bases and sources of the calculation of the data of the RELAP5-3D code were documented. Included in the data file are Part 1: Volumes; Part 2: Junctions; Part 3: Heat Structures; and Part 4: Control Volumes. The setting-up of the input date file for RELAP5-3D of the Third Nuclear Power Station was based on the conversion and re-verification of the data documented in the input data file for RELAP-MOD3 of the same plant. In the input data file of the Third Nuclear Power Station, the realistic plant control systems of importance were simulated. These include (1) the pressurizer heater and spray valve control system to adjust the pressure on the primary side, (2) the 3-variable (i.e., narrow-range water level of the steam-generator, feedwater flow rate, and steam flow rate) feedwater control system for the water level of the steam-generator, (3) the steam discharge system, and (4) the over-temperature temperature-differential and over-load temperature-differential trip protection systems, and (5) other trip protection systems. Overall speaking, this study used the best-estimate capability of the RELAP5-3D code to simulate the two transient events of the two plants. The results obtained from these simulations indicated that the calculated results obtained from the codes were in excellent agreement (within 1%) with those from the plant data. Besides, the trends of the time-varying curves of important parameters obtained from the codes’ calculations were in agreement with those obtained from the recorded data of the plants.

並列關鍵字

Transient Events ； Kuosheng ； Maanshan

參考文獻

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