透過您的圖書館登入
IP:3.22.66.208
  • 學位論文

超臨界水反應器RELAP5/MOD3穩態輸入數據建立與暫態分析

Transient Analyses of Supercritical Water Reactor using RELAP5/MOD3

指導教授 : 李敏

摘要


第四代核反應器是新型態的核反應器,可望提供永續、穩定且經濟的能源,並大幅度改善電廠安全。超臨界水反應器是其中之一,具有高熱功率,系統簡單等特質,加上超臨界水燃煤電廠、壓水式核反應器與沸水式核反應器的豐富運轉資訊作為參考,為具有發展潛力的反應器。 本研究的目標,是使用RELAP5/MOD3程式,建立超臨界水反應器之穩態輸入數據以及暫態分析。RELAP5/MOD3是愛達荷國家工程實驗室(INEL)與美國核能管制委員會(NRC)合作發展的熱水流分析程式,為輕水式核反應器所用。本論文之穩態輸入參數,根據美國愛達荷國家實驗室於2005年一月發表的報告所提供之超臨界水反應器設計參數。模擬範圍包含反應器壓力槽及內部組件、熱端管路、冷端管路部份。 本論文暫態分析選擇喪失主要飼水事故(Loss of Main Feedwater, LOMF)。在適當的安全系統設計之下,暫態發生後的燃料護套最大溫度可維持在法規限值840℃之下,然而分析程式RELAP5/MOD3的熱傳模式有缺陷,導致無法預測後續暫態反應。

並列摘要


The Supercritical Water Reactor (SCWR), one of the six possible types of Gen-IV reactor, is a Light Water Reactor (LWR) operating at supercritical pressure. It has the advantage of high thermal efficiency, plant system simplifications and proven technologies. In this study, RELAP5/MOD3 code is used to simulate the steady state of the SCWR and to analyze the transients. The components considered in the input deck include SCWR core, 2 loop hot legs, cold legs, and safety components. Analyses have shown that a transient caused by a Loss of Main Feedwater (LOMF) event can be a challenging event for a SCWR. The propose of the safety system is to make the peak cladding temperature remain less than the transient limit 840℃. Due to some defect of the heat transfer model of RELAP5/MOD3 code, the transient analyses are not complete.

並列關鍵字

SCWR RELAP5/MOD3 HASH(0x1baea7d0)

參考文獻


1. Gen-IV annual report 2007
2. I.L. Pioro, H.F. Khartabil, R.B. Duffey, “Heat transfer to supercritical fluids flowing in channels – empirical correlations (survey),” Nuclear Engineering and Design, 230 (2004) 69-91
3. Philip MacDonald, Jacopo Buongiorno, James W. Sterbentz, Cliff Davis, Robert Witt Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, INEEL/EXT-04-02530, January, 2005
4. NIST化學資料庫網站位置:http://webbook.nist.gov/chemistry/fluid/
5. Jacopo Buongiorno, Philip E. MacDonald, “Progress report for the FY-03 generation-IV R&D activities for the development of the SCWR in the U.S.” INEEL/EXT-03-01210, September 30, 2003

延伸閱讀