针对AP1000核电站,基于两流体最佳估算系统程序RELAP5建立热工水力模型,基于Matlab/Simulink软件及工业组态软件建立相关控制系统数学模型,用于对正常给水丧失事故的计算分析。建模数据主要参考AP1000Design Control Document(AP1000DC...针对AP1000核电站,基于两流体最佳估算系统程序RELAP5建立热工水力模型,基于Matlab/Simulink软件及工业组态软件建立相关控制系统数学模型,用于对正常给水丧失事故的计算分析。建模数据主要参考AP1000Design Control Document(AP1000DCD),由于建模数据不够充分、详尽,模型不够精确,文中事故分析以定性分析为主。计算结果表明:RELAP5具备计算自然循环的能力,计算结果与DCD中正常给水丧失事故结果总体趋势基本一致,非能动余热排出系统(PRHRS)、堆芯补水箱(CMT)系统能够及时、有效地排出堆芯余热和堆芯衰变热,确保堆芯安全。PRHRS余热排出能力对事故发展有明显影响,模型中PRHRS余热排出能力较强,使冷却剂温度更快地降低到较低水平,导致CMT更早投入以及随后反应堆各参数响应的不同。展开更多
Three different kinds of experiments and their typical results are surveyed for the passive residual heat removal system (PRHRS) of PWR performed in Nuclear Power Institute of China (NPIC) recent ten years. The typi- ...Three different kinds of experiments and their typical results are surveyed for the passive residual heat removal system (PRHRS) of PWR performed in Nuclear Power Institute of China (NPIC) recent ten years. The typi- cal results of MISAP, a special code for PWR passive residual heat removal system developed and assessed by NPIC, are also described briefly in this paper.展开更多
Researching parameters correlation is important to analysis of reliability uncertainty for passive system. The only criterion for traditional method to determine the parameters correlation is the correlation coefficie...Researching parameters correlation is important to analysis of reliability uncertainty for passive system. The only criterion for traditional method to determine the parameters correlation is the correlation coefficient threshold. This method is subjective and needs improvement. Taking loss of normal feedwater accident of AP1000 passive residual heat removal system( PRHRS)as example,a comprehensive method was proposed to resolve the subjectivity problem of traditional method. Comprehensive method took account of scatter diagram of parameters and thermal transmission rule and significance testing of correlation coefficient comprehensively when judging parameters correlation. By comparing the effect of parameters judged by traditional and comprehensive methods respectively, we found the distance of traditional method was larger than that of comprehensive method,showing some parameters impacting thermal transmission rule removed by traditional method and comprehensive method could judge more precise and scientific parameters. So comprehensive method should be used to judge linear relation between parameters and thermal transmission rule.展开更多
The transient performance and optimization of a passive residual heat removal heat exchanger(PRHR HX)were investigated.First,a calculation method was developed for predicting the heat transfer of the PRHR HX.The calcu...The transient performance and optimization of a passive residual heat removal heat exchanger(PRHR HX)were investigated.First,a calculation method was developed for predicting the heat transfer of the PRHR HX.The calculation results were validated through comparisons with ROSA experimental data.The heat-transfer performance of the AP1000 PRHR HX in the initial period was predicted,and it satisfied the design requirements.Second,the distributions of the heat flux,tube-inside/outside heattransfer coefficients,and heat load for the AP1000 PRHR HX over 2000 s were examined.Third,an optimization study was conducted by adjusting the horizontal length and tube diameter.Their effects on the four main heat-transfer parameters and the heat-transfer area were analyzed.Furthermore,the influence of the initial in-containment refueling water storage tank(IRWST)temperature was investigated using an established simulation procedure.The results indicated that it significantly affected the trends of the IRWST temperature and reactor outlet temperature.Finally,the minimum required flow rates over time to maintain the reactor outlet temperature at the safety line were determined for different start-up times.The trends of the minimum required flow rate and the peak flow rate were analyzed.展开更多
文摘针对AP1000核电站,基于两流体最佳估算系统程序RELAP5建立热工水力模型,基于Matlab/Simulink软件及工业组态软件建立相关控制系统数学模型,用于对正常给水丧失事故的计算分析。建模数据主要参考AP1000Design Control Document(AP1000DCD),由于建模数据不够充分、详尽,模型不够精确,文中事故分析以定性分析为主。计算结果表明:RELAP5具备计算自然循环的能力,计算结果与DCD中正常给水丧失事故结果总体趋势基本一致,非能动余热排出系统(PRHRS)、堆芯补水箱(CMT)系统能够及时、有效地排出堆芯余热和堆芯衰变热,确保堆芯安全。PRHRS余热排出能力对事故发展有明显影响,模型中PRHRS余热排出能力较强,使冷却剂温度更快地降低到较低水平,导致CMT更早投入以及随后反应堆各参数响应的不同。
文摘Three different kinds of experiments and their typical results are surveyed for the passive residual heat removal system (PRHRS) of PWR performed in Nuclear Power Institute of China (NPIC) recent ten years. The typi- cal results of MISAP, a special code for PWR passive residual heat removal system developed and assessed by NPIC, are also described briefly in this paper.
基金Nuclear Reactor System Design Technology Foundation of National Key Laboratory,China(No.HT-JXYY-02-2014002)
文摘Researching parameters correlation is important to analysis of reliability uncertainty for passive system. The only criterion for traditional method to determine the parameters correlation is the correlation coefficient threshold. This method is subjective and needs improvement. Taking loss of normal feedwater accident of AP1000 passive residual heat removal system( PRHRS)as example,a comprehensive method was proposed to resolve the subjectivity problem of traditional method. Comprehensive method took account of scatter diagram of parameters and thermal transmission rule and significance testing of correlation coefficient comprehensively when judging parameters correlation. By comparing the effect of parameters judged by traditional and comprehensive methods respectively, we found the distance of traditional method was larger than that of comprehensive method,showing some parameters impacting thermal transmission rule removed by traditional method and comprehensive method could judge more precise and scientific parameters. So comprehensive method should be used to judge linear relation between parameters and thermal transmission rule.
基金supported by the Shanghai Nuclear Engineering Research and Design Institute,State Power Investment Corporation
文摘The transient performance and optimization of a passive residual heat removal heat exchanger(PRHR HX)were investigated.First,a calculation method was developed for predicting the heat transfer of the PRHR HX.The calculation results were validated through comparisons with ROSA experimental data.The heat-transfer performance of the AP1000 PRHR HX in the initial period was predicted,and it satisfied the design requirements.Second,the distributions of the heat flux,tube-inside/outside heattransfer coefficients,and heat load for the AP1000 PRHR HX over 2000 s were examined.Third,an optimization study was conducted by adjusting the horizontal length and tube diameter.Their effects on the four main heat-transfer parameters and the heat-transfer area were analyzed.Furthermore,the influence of the initial in-containment refueling water storage tank(IRWST)temperature was investigated using an established simulation procedure.The results indicated that it significantly affected the trends of the IRWST temperature and reactor outlet temperature.Finally,the minimum required flow rates over time to maintain the reactor outlet temperature at the safety line were determined for different start-up times.The trends of the minimum required flow rate and the peak flow rate were analyzed.
