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  • 學位論文

龍門電廠穩定性分析方法論建立與應用

Establishment and Application of Stability Analysis Methodology for LUNGMEN ABWR

指導教授 : 施純寬
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摘要


沸水式電廠在高功率低流量狀態下,容易發生熱水力與中子回饋結合的不穩定現象,一般使用頻域分析方法來界定穩定運轉邊界,避免運轉時進入不穩定區。本研究使用美國NRC認可之頻域計算穩定性分析程式LAPUR6.0來進行穩定性分析,由於龍門電廠爐心具有較多的燃料組件,原LAPUR6.0方法論利用12群燃料束分區來模擬爐心穩定性的方法已不敷使用。本研究目的在於參考原12分區分析方法論的建立,再依照爐心燃料束幾何位置與對稱原則發展針對龍門電廠之穩定性方法論,將燃料束分成200群 (LAPUR6.0的最大分區能力) 進行分析,並透過此分區方法發展自動分區程式EXAVERA_200。文中首先介紹LAPUR6.0分析程序,然後說明龍門電廠燃料束分區規劃原則與輸入檔編輯,透過本分析方法論與國外ABWR研究設施SIRIUS-F模擬結果進行分析比較,並驗證本方法論具有模擬分析龍門ABWR的能力。最後利用此分析方法論探究其應用性,分別為探討龍門電廠功率流量圖上的衰減率分布,以及模擬特殊暫態之穩定性。透過分析功率流量圖的衰減率分布可發現龍門電廠運轉範圍內皆是處於相當穩定的情況,即使運轉進入BWROG方案一之不穩定限制區,其衰減率仍處於安全範圍;另外FSAR提及ATWS暫態事件可能造成功率震盪現象,本研究利用TRACE/PARCS之類似模擬結果進行穩定性分析,並得到與FSAR相同之結論,即此功率震盪仍不構成爐心不穩定性現象。本研究之分析原藉由自動化程式DRASM進行LAPUR6.0輸入檔建立與收斂結果,透過這次新方法論的建立一併將自動化程式DRASM更新成介面化程式,並可使用12分區與200分區兩種方法論。

關鍵字

龍門電廠 穩定性分析 LAPUR

並列摘要


BWRs may encounter some stability and safety problems due to the presence of steam in the reactors core. The instability is coupled mechanisms of two-phase flow thermal-hydraulic and neutronic behaviors. In order to investigate the stability phenomena, we uses the NRC certified code, LAPUR6.0, to calculate the decay ratio of specific power/flow condition. Owing to the assemblies used in Lungmen ABWR are much more than Chinshan and Kuosheng nuclear power station, the old methodology of LAPUR6.0 may need to be updated. For example, the grouping number in LAPUR6.0 was increased from 12 to 200. The object of this thesis is to develop the new methodology of LAPUR6.0 for Lungmen ABWR, and the application of this methodology. First, this paper illustrates the new methodology and the assemblies grouping method in detail, and shows the decks of LAPUR6.0 input parameters. In this research, the stability phenomena were investigated along the rod lines and pump speed lines by LAPUR6.0 for validating with the SIRIUS-F experimental results. The application of this methodology is divided into two parts, the decay ratio distribution on Lungmen ABWR power/flow map and the stability analysis for ATWS instability event, described by FSAR. According to the decay ratio distribution, it can be found that the core system remains stable under operating condition and the least damped region (Region III) on power/flow map. This thesis analyzed the ATWS event condition from TRACE/PARCS result, and the decay ratio of this event agrees well with FSAR result, the system returns to stable after power oscillation. All the analysis processes in this research were operated by DRASM200 interphase program, based on the old automatic program, DRASM.

並列關鍵字

無資料

參考文獻


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[8] Hashimoto Kengo, “Linear Modal Analysis of Out-Of-Phase Instability in Boiling Water Reactor Cores”, Ann. Nucl. Energy, Vol. 20, No. 12, pp. 789-797, 1993

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