雙RELAP5核能電廠系統動態模擬與分析工作平台製作技術之發展與應用

Development and Application of Dual RELAP5 Whole Plant Dynamic Simulation Platform for Nuclear Power Plant

楊宗祐(Yang, Chung Yu)

指導教授 ： 施純寬 ； 陳紹文

國立清華大學/原子科學院/核子工程與科學研究所/博士(2015年)

摘要

本研究整合核能電廠之安全分析技術及系統模擬技術，制定一套標準化的程序，用以製作雙RELAP5電廠系統動態模擬與分析工作平台。本研究制定之工作平台製作程序包括：工作平台製作流程、RELAP5計算模組執行檔編譯程序、個別模式建立與驗證程序、模式整合程序等。本研究以龍門電廠為對象，製作電廠專屬的雙RELAP5電廠系統動態模擬與分析工作平台，用以驗證及確認所制定之工作平台製作標準化程序的可施行性。
雙RELAP5核能電廠系統動態模擬與分析工作平台，以商用視窗化之電腦模擬平台為基礎架構。工作平台整併了二個RELAP5計算模組，一個RELAP5模組用以模擬反應器系統及圍阻體系統的雙相熱水流現象，並用以計算爐心核燃料的中子物理反應；而另一個RELAP5模組則用以模擬功率轉換系統的雙相熱水流現象。電廠之控制系統、安全保護系統，以及資訊監測系統，使用平台內建的控制邏輯演算模組及熱水流計算模組進行模擬。
本研究成功製作完成龍門電廠專屬之雙RELAP5電廠系統動態模擬與分析工作平台，完成所制定工作平台製作標準化程序之可施行性的驗證與確認。工作平台具備設計之模擬與計算能力，本研究使用工作平台，成功完成多項支援電廠起動測試的應用。工作平台之應用項目包括：汽機帶動飼水泵性能曲線提供、飼水控制系統起動測試模擬、汽機帶動飼水泵流量需求與速度需求對應關係提供、功率測試模擬與比對等。
為了擴展龍門電廠專屬之雙RELAP5電廠系統動態模擬與分析工作平台的應用範圍，本研究完成RELAP5計算能力的精進，以及RELAP5模式的更新。本研究完成RELAP5程式之均質平衡臨界流計算能力的建立與驗證。此外，本研究根據最新的電廠功率轉換系統熱平衡資料，完成功率轉換系統RELAP5模擬模式的更新與驗證。

關鍵字

核能電廠 ； 模擬器 ； 功率轉換系統 ； 均質平衡臨界流模式

並列摘要

In this study, the safety analysis technology and the system simulation technology for the nuclear power plant were integrated and a set of standardized procedures were created to build a dual RELAP5 whole plant simulation and analysis platform (the dual RELAP5 platform). The designed procedures are the platform development flowchart, the RELAP5 module execution file generation procedure, the implementation and verification procedure of the plant system simulation model, and the integration procedure of the plant system models.
The Lungmen plant-specific dual RELAP5 platform (the Lungmen platform) was built successfully in this study. The development of the Lungmen platform was to verify the workability of the created standardized procedures. A commercial Windows-based computer simulation platform was used as the base of the Lungmen platform. There are two RELAP5 modules in the Lungmen platform. They are used to simulate the thermal-hydraulic phenomena in the reactor system, the containment system, and the power conversion system and to calculate the kinetic responses in the reactor core. The control systems, the safety protection systems, and the monitoring systems of the Lungmen plant were modeled using the platform built-in modules.
The Lungmen platform has the designed simulation and calculation capabilities. It was applied successfully to support the plant startup test. The applications are the turbine-driven reactor feedwater pump performance curve calculations, the startup test simulations of the feedwater control system, the function table generations for the turbine-driven reactor feedwater pump flow demand and speed demand conversion, and the plant power test simulations and comparisons.
In order to extend the applications of the Lungmen platform, the capability of the RELAP5 code and the simulation of the RELAP5 model were improved. The homogeneous equilibrium critical flow model was merged into the RELAP5 code. And the power conversion system RELAP5 simulation model of the Lungmen platform was updated according to the most up-to-date plant heat balance data.

並列關鍵字

Nuclear Power Plant ； Simulator ； Power Conversion System ； Homogeneous Equilibrium Critical Flow Model

參考文獻

[2] K.S. Liang, et al., “Modeling of A Power Conversion System with RELAP5-3D/K and Associated Application to the Feedwater Blowdown Licensing Analysis for the ABWR Containment Design,” Nuclear Technology, vol. 153, 2006, pp. 184-196.

[4] K.S. Liang, et al., “Analysis of A Coupled Blowdown from Both RPV and BOP with RELAP5-3D/K for A Limiting FWLB of An ABWR for Containment Design,” Nuclear Technology, vol. 169, 2010, pp. 50-60.

[5] K.S. Liang, et al., “Analysis of Low-Pressure ECC Injection Bypass of An ABWR during A Feedwater Line Break with RELAP5-3D/K,” Nuclear Technology, vol. 166, 2009, pp. 146-155.

[7] K.S. Liang, et al., “Analysis of ABWR FW Pump Performance during Power Ascending and Verification of An Operational Strategy to Jump Pump Speed across the Critical Region with RELAP5-3D,” Annals of Nuclear Energy, vol. 36, 2009, pp. 917-922.

[8] H.O. Kang, et al., “Fully-coupled Transient Simulation for RCS and SPCS of An Integral Reactor Plant,” Annals of Nuclear Energy, vol. 37, 2010, pp. 412-421.