TRACE程序在国产先进压水堆核电厂小破口失水事故计算中的应用
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摘要
本文利用反应堆热工水力软件TRACE对三回路国产先进压水堆发生小破口失水事故进行模拟计算,得到事故过程中反应堆系统压力、水位、破口流量的变化和安注系统的投入情况,将计算结果与CATHARE程序的计算结果进行对比、分析和讨论,两程序计算结果在趋势上较符合,验证了TRACE程序在计算小破口事故的准确性。
In this paper SB-LOCA accident calculation of three-loop Domestic Advanced PWR is carried out by the reactor thermal hydraulic code of TRACE,the results include reactor system pressure,core water level,break flow rate and safety injection system operating condition.Further the calculation results are compared with the ones got with CATHARE code to make verification that whether the results we got are correct.
In this paper SB-LOCA accident calculation of three-loop Domestic Advanced PWR is carried out by the reactor thermal hydraulic code of TRACE,the results include reactor system pressure,core water level,break flow rate and safety injection system operating condition.Further the calculation results are compared with the ones got with CATHARE code to make verification that whether the results we got are correct.
引文
[1]TRACE V5.0 USER'S MANUAL[R].U.S.Nuclear Regulatory Commission,2010.
[2]Jong-Rong Wang,Hao-Tzu Lin,Chunkuan Shih.Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant[R].Office of Nuclear Regulatory Research U.S.Nuclear Regulatory Commission,Washington,DC,20555-0001,2010.6.
[3]M.Avramova,A.Velazquez-Lozada,A.Rubin1.Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database[J].Science and Technology of Nuclear Installations,2012,2013(6).
[4]Jong-Rong Wang,Hao-Tzu Lin,Chunkuan Shih.Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant[R].U.S.Nuclear Regulatory Commission.NUREG/IA-0241.
[5]冯进军,胡威,周克峰,等.用PARCS/TRACE/ROBIN程序系统研究秦山二期弹棒事故[J].核科学与工程,2015(3).
[6]俞尔俊,李吉根.核电厂核安全[M].北京:原子能出版社,2010:125-132.
[7]黄彦平、曹念、文彦,等.CATHARE程序的主要特征及应用[J].核动力工程,2003,12:540-544.
[8]TRACE V5.0THEORY MANUAL[R].U.S.Nuclear Regulatory Commission,2010.
[9]Symbolic Nuclear Analysis Package(SNAP)User's Manual[R].Applied Programming Technology,Inc.
[2]Jong-Rong Wang,Hao-Tzu Lin,Chunkuan Shih.Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant[R].Office of Nuclear Regulatory Research U.S.Nuclear Regulatory Commission,Washington,DC,20555-0001,2010.6.
[3]M.Avramova,A.Velazquez-Lozada,A.Rubin1.Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database[J].Science and Technology of Nuclear Installations,2012,2013(6).
[4]Jong-Rong Wang,Hao-Tzu Lin,Chunkuan Shih.Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant[R].U.S.Nuclear Regulatory Commission.NUREG/IA-0241.
[5]冯进军,胡威,周克峰,等.用PARCS/TRACE/ROBIN程序系统研究秦山二期弹棒事故[J].核科学与工程,2015(3).
[6]俞尔俊,李吉根.核电厂核安全[M].北京:原子能出版社,2010:125-132.
[7]黄彦平、曹念、文彦,等.CATHARE程序的主要特征及应用[J].核动力工程,2003,12:540-544.
[8]TRACE V5.0THEORY MANUAL[R].U.S.Nuclear Regulatory Commission,2010.
[9]Symbolic Nuclear Analysis Package(SNAP)User's Manual[R].Applied Programming Technology,Inc.