非能动余热排出系统敏感性分析
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摘要
以中国改进型压水堆核电站CPR1000为研究对象,在其蒸汽发生器二次侧设计了一套非能动余热排出系统(PRHRS),该系统采用在蒸汽发生器二次侧建立自然循环的方式间接带走堆芯余热,确保事故条件下堆芯安全。用RELAP5/MOD3.2程序对系统进行了合理的简化并建模,在全场断电(SBO)事故条件下模拟了PRHRS的瞬态响应过程,并对高位水箱的容积、PRHRS换热器的换热面积、冷热中心高度差以及PRHRS的投入时间等影响PRHRS工作特性的相关参数进行了敏感性分析。计算结果表明:增加高位水箱的容积和增大换热面积均有助于二次侧余热排出系统带走一回路的堆芯余热;降低冷热中心高度差对PRHRS的自然循环能力影响不大;余热排出系统投入时间越早,蒸汽发生器二次侧水位越高,越有利于一次侧余热的排出。
A new passive residual heat removal system(PRHRS) on the secondary side of the steam generator was designed for CPR1000,which can remove residual heat in the core by natural circulation in the secondary side of steam generator and ensure core safety under accident conditions.The model of the simplified system for CPR1000 was established by using RELAP5/MOD3.2 code,and the transient characteristic of PRHRS was simulated under the station blackout(SBO) accident.The sensitivity analysis was performed for the related parameters which affect the working characteristics of PRHRS,such as the volume of high-level tanks,area of heat exchanger,height difference of cold and hot centers and the initiating time of PRHRS.The calculation results show that increasing volume of high-level tanks and area of heat exchanger helps to remove residual heat of the core;but reducing height difference of cold and hot centers has little influence on the capacity of natural circulation for PRHRS;the earlier the initiation of PRHRS is,the higher the water level in the secondary side of steam generator is,the better the PRHRS removes residual heat in the core.
A new passive residual heat removal system(PRHRS) on the secondary side of the steam generator was designed for CPR1000,which can remove residual heat in the core by natural circulation in the secondary side of steam generator and ensure core safety under accident conditions.The model of the simplified system for CPR1000 was established by using RELAP5/MOD3.2 code,and the transient characteristic of PRHRS was simulated under the station blackout(SBO) accident.The sensitivity analysis was performed for the related parameters which affect the working characteristics of PRHRS,such as the volume of high-level tanks,area of heat exchanger,height difference of cold and hot centers and the initiating time of PRHRS.The calculation results show that increasing volume of high-level tanks and area of heat exchanger helps to remove residual heat of the core;but reducing height difference of cold and hot centers has little influence on the capacity of natural circulation for PRHRS;the earlier the initiation of PRHRS is,the higher the water level in the secondary side of steam generator is,the better the PRHRS removes residual heat in the core.
引文
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[3]阎义洲,臧希年.AC600核电站断电事故分析[J].中国电力,2001,34(11):20-23.YAN Yizhou,ZANG Xinian.Blackout accidentanalyses of AC600nuclear power plant[J].Elec-tric Power,2001,34(11):20-23(in Chinese).
[4]沈瑾,江光明,唐钢,等.一体化先进堆全厂断电事故下非能动余热排出系统能力分析[J].核动力工程,2007,28(6):80-83.SHEN Jin,JIANG Guangming,TANG Gang,etal.Performance analysis of passive residual heatremoval system under blackout accident of Chi-nese integral advanced reactor[J].Nuclear PowerEngineering,2007,28(6):80-83(in Chinese).
[5]彭云康,李夔宁,童明伟,等.RELAP5分析非能动堆芯应急冷却系统实验结果[J].重庆大学学报,2003,26(3):85-87.PENG Yunkang,LI Kuining,TONG Mingwei,et al.RELAP5analysis of passive emergencycore cooling system tests[J].Journal ofChongqing University,2003,26(3):85-87(inChinese).
[6]于雷,谢海燕,桂学文,等.采用非能动余热排出系统实验数据对RELAP5程序的评价[J].原子能科学技术,2008,42(8):678-684.YU Lei,XIE Haiyan,GUI Xuewen,et al.As-sessment of RELAP5 code by experiments ofpassive residual heat removal system[J].AtomicEnergy Science and Technology,2008,42(8):678-684(in Chinese).
[7]XU Y,ISHII M,FELTUS M A.Safety analysisof multiple-failure of passive safety systems inSBWR-1200SBLOCA[J].Nuclear Engineeringand Design,2004,230:107-119.
[8]HART J,SLEGERS W J M,de BOER S L,etal.TEPSS-Technology enhancement for passivesafety systems[J].Nuclear Engineering and De-sign,2001,209:243-252.
[9]ANDRITSOS F,ANGELINI A,BARTELS HW,et al.SEAFP:Passive removal of the decayheat[J].Fusion Engineering and Design,1995,29:193-197.
[10]CHUNG Y J,YANG S H,KIM H C,et al.Thermal hydraulic calculation in a passive residu-al heat removal system of the SMART-P plantfor forced and natural convection conditions[J].Nuclear Engineering and Design,2004,232:277-288.
[11]徐钊,吴莘馨.200MW低温核供热堆非能动余热排出系统动态分析[J].核动力工程,2008,29(2):61-65.XU Zhao,WU Xinxin.Transient analysis of re-sidual heat removal system used in 200 MW lowtemperature heating reactor[J].Nuclear PowerEngineering,2008,29(2):61-65(in Chinese).
[12]SATO T,OIKAWA H,AKINAGA M,et al.Different variations of a passive safety contain-ment for a BWR with active and passive safetysystems[J].Nuclear Engineering and Design,2005,235:2 125-2 139.
[13]XIAO Zejun,ZHUO Wenbin,ZHENG Hua,etal.Experimental research progress on passivesafety systems of Chinese advanced PWR[J].Nuclear Engineering and Design,2003,225:305-313.
[14]黄彦平,卓文彬,杨祖毛,等.先进压水堆非能动余热排出技术试验研究[J].核动力工程,2003,24(1):18-23.HUANG Yanping,ZHUO Wenbin,YANG Zu-mao,et al.Experimental research on passive re-sidual heat remove system for advanced PWR[J].Nuclear Power Engineering,2003,24(1):18-23(in Chinese).
[15]臧希年,申世飞.核电厂系统及设备[M].北京:清华大学出版社,2003:337.