中国铅基研究堆非能动余热排出系统可靠性分析
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摘要
铅冷快堆是第四代核能系统推荐堆型之一,世界上多个铅冷快堆采用非能动余热排出系统。非能动系统中作为驱动的自然力与阻力在数量级上接近,由周边环境、材料参数的变化引起的波动不可忽略,因此需要研究非能动系统可靠性。改进了常用的响应面分析法,并应用于中国铅基研究堆反应堆容器空气冷却系统(Reactor Vessel Air Cooling System,RVACS)中。分析中使用流体计算软件Fluent模拟中国铅基研究堆RVACS系统的余热排出过程,研究了输入参数的不确定性对系统可靠性及反应堆安全产生的影响。在大量模拟数据的基础上结合神经网络法建立了输入参数不确定性和结果不确定性之间的映射关系,并以此分析RVACS非能动失效概率。分析结果表明在全厂断电的情况下,RVACS四组并联排热管中的两组也能够可靠地导出反应堆余热。
Background: Because of the safety and the competition in economy,Generation IV reactors represent the development tendency of innovative nuclear systems.Lead cooled fast reactor is a variety of Generation IV reactors and many of them around the world adopt passive systems to remove residual heat.Purpose: The driving force of passive system is approximate at the same level of resistance,so an analysis on the reliability of passive system becomes necessary.Methods: This study made some improvements of the response surface method and applied it to Reactor Vessel Air Cooling System(RVACS) of China lead-based research reactor(CLEAR-I).During the analysis,the process of removing residual heat of RVACS was simulated by Fluent in order to find out how inputs would affect the safety of reactor.On the base of a mass of simulations,this study established relationships between inputs and outputs to find failure probability of RVACS.Results: The advanced response surface method raised the sampling efficiency for small-probability events by as much as four times.Through this method,we got the failure probability of RVACS.Conclusion: The results showed that two of four sets RVACS pipes can safely remove residual heat of reactor during loss of power.
Background: Because of the safety and the competition in economy,Generation IV reactors represent the development tendency of innovative nuclear systems.Lead cooled fast reactor is a variety of Generation IV reactors and many of them around the world adopt passive systems to remove residual heat.Purpose: The driving force of passive system is approximate at the same level of resistance,so an analysis on the reliability of passive system becomes necessary.Methods: This study made some improvements of the response surface method and applied it to Reactor Vessel Air Cooling System(RVACS) of China lead-based research reactor(CLEAR-I).During the analysis,the process of removing residual heat of RVACS was simulated by Fluent in order to find out how inputs would affect the safety of reactor.On the base of a mass of simulations,this study established relationships between inputs and outputs to find failure probability of RVACS.Results: The advanced response surface method raised the sampling efficiency for small-probability events by as much as four times.Through this method,we got the failure probability of RVACS.Conclusion: The results showed that two of four sets RVACS pipes can safely remove residual heat of reactor during loss of power.
引文
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14 龚频,汤晓斌,陈达.多项式拟合法设定辐照灭菌剂量的研究[J].核技术,2014,37(11):110202GONG Pin,TANG Xiaobin,CHEN Da.Study on setting the sterilization dose by polynomial fitting method[J].Nuclear Techniques,2014,37(11):110202
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16 吴宜灿,黄群英,朱志强,等.中国系列液态锂铅实验回路设计与研发进展[J].核科学与工程,2009,29(2):163 -171WU Yican,HUANG Qunying,ZHU Zhiqiang,et al.Progress in design and development of series liquid lithium-lead experimental loops in China[J].Nuclear Science and Engineering,2009,29(2):163-171
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18 Wu Y,FDS Team.Conceptual design of the China fusion power plant FDS-II[J].Fusion Engineering and Design,2008,83(10-12):1683-1689
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20 Wu Y,FDS Team.Conceptual design activities of FDS series fusion power plants in China[J].Fusion Engineering and Design,2006,81(23-24):2713-2718
21 Wu Y.Progress in fusion-driven hybrid system studies in China[J].Fusion Engineering and Design,2002,63-64(1):73-80
22 Wu Y,FDS Team.Design analysis of the China Dual-Functional Lithium Lead(DFLL)test blanket module in ITER[J].Fusion Engineering and Design,2007,82(1):1893-1903
23 盛美玲,金鸣,柏云清,等.中国铅合金冷却研究堆事故余热排出系统概念设计与分析[J].核科学与工程,2014,34(1):91-96SHENG Meiling,JIN Ming,BAI Yunqing,et al.Preliminary design and analysis of emergency decay heat removal system for China lead alloy cooled research reactor[J].Nuclear Science and Engineering,2014,34(1):91-96
24 Ye C,Zheng M G,Wang Y,et al.Study on the long-term passive cooling extension of AP1000 reactor[J].Nuclear Science and Techniques,2013,24(4):040601
25 Cao R F,Wu Y C,Pei X,et al.Multi-objective optimization of inverse planning for accurate radiotherapy[J].Chinese Physics C,2011,35(3):313-317
26 王强龙.加速器驱动次临界堆始发事件及非能动安全特性初步研究[D].合肥:中国科学技术大学,2013,Doi:10 .7666/d.Y2354113WANG Qianglong.Preliminary research on initial events and passive safety characteristics of accelerator driven system-reactor[D].Hefei:University of Science and Technology of China,2013,Doi:10.7666/d.Y2354113
27 蔡琦,郁军,金家善,等.核动力装置运行过程可靠性研究现状与发展[J].核技术,2002,25(3):235-240CAI Qi,YU Jun,JIN Jiashan,et al.Current situation and development on reliability analysis of operation process in the nuclear power plant[J].Nuclear Techniques,2002,25(3):235-240
28 田雨,雷晓辉,蒋云钟,等.水文模型参数敏感性分析方法研究评述[J].水文,2010,30(4):9-12+62TIAN Yu,LEI Xiaohui,JIANG Yunzhong,et al.Comment on parameter sensitivity analysis of hydrological model[J].Journal of China Hydrology,2010,30 (4):9-12+62
2 Maes D.Mechanical design of the small-scale experimental ADS:MYRRHA[C].12th International Conference on Emerging Nuclear Energy Systems,Brussels,2005
3 Zrodnikov A V,Toshinsky G I,Komlev O G,et al.Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100[J].Nuclear Engineering and Design,2006,236(14):1490-1520
4 Burgazzi L.Evaluation of uncertainties related to passive systems performance[J].Nuclear Engineering and Design,2004,230(1-3):93-106
5 Kirchsteiger C.A new approach to quantitative assessment of reliability of passive systems[J].Safety Science,2005,43(10):771-777
6 Auria F D,Giannotti W.Development of a code with the capability of internal assessment of uncertainty[J].Nuclear Technology,2000,131(2):159-196
7 谢国锋,童节娟,何旭洪,等.用Monte Carlo方法计算HTR-10余热排出系统物理过程的失效概率[J].核动力工程,2008,29(2):85-87XIE Guofeng,TONG Jiejuan,HE Xuhong,et al.Calculation of physical failure probability of HTR-10residual heat removal system by Monte Carlo method[J].Nuclear Power Engineering,2008,29(2):85-87
8 谢国锋,何旭洪,童节娟,等.响应面方法计算HTR-10余热排出系统物理过程的失效概率[J].物理学报,2007,56(6):3192-3197XIE Guofeng,HE Xuhong,TONG Jiejuan,et al.Calculating physical failure probability of HTR-10’s residual heat removal system by response surface method[J].Acta Physica Sinica,2007,56(6):3192-3197
9 周文俊,贾宝山,俞冀阳.压力管式反应堆非能动余热排出系统方案研究[J].核技术,2003,26(7):523-526ZHOU Wenjun,JIA Baoshan,YU Jiyang.Conceptual study of passive residual heat removal system of a pressure tube water reactor[J].Nuclear Techniques,2003,26(7):523-526
10 肖玲梅,于涛,余红星,等.自适应蒙特卡罗方法计算海水淡化堆非能动系统物理过程失效概率[J].核动力工程,2010,31(1):61-64XIAO Lingmei,YU Tao,YU Hongxing,et al.Calculation of physical process failure probability of passive systems in NDR by adaptive Monte Carlo method[J].Nuclear Power Engineering,2010,31(1):61-64
11 吴宜灿,柏云清,宋勇,等.中国铅基研究反应堆概念设计研究[J].核科学与工程,2014,34(2):201-208WU Yican,BAI Yunqing,SONG Yong,et al.Conceptual design of China lead-based research reactor CLEAR-I[J].Nuclear Science and Engineering,2014,34(2):201-208
12 Wu Y,Zheng S,Zhu X,et al.Conceptual design of the fusion-driven subcritical system FDS-I[J].Fusion Engineering and Design,2006,81(8-14):1305-1311
13 陈颖,宁佐贵.基于神经网络响应面法的随机结构动力可靠度分析[J].振动与冲击,2007,26(1):65-68CHEN Ying,NING Zuogui.Dynamic reliability analysis of a stochastic structure with neural network response surface method[J].Journal of Vibration and Shock,2007,26(1):65-68
14 龚频,汤晓斌,陈达.多项式拟合法设定辐照灭菌剂量的研究[J].核技术,2014,37(11):110202GONG Pin,TANG Xiaobin,CHEN Da.Study on setting the sterilization dose by polynomial fitting method[J].Nuclear Techniques,2014,37(11):110202
15 叶志民,张鹏,刘峙嵘.基于蒙特卡罗均匀化的堆物理分析方法[J].核技术,2014,37(6):060603YE Zhimin,ZHANG Peng,LIU Zhirong.Reactor physics analysis method based on Monte Carlo homogenization[J].Nuclear Techniques,2014,37(6):060603
16 吴宜灿,黄群英,朱志强,等.中国系列液态锂铅实验回路设计与研发进展[J].核科学与工程,2009,29(2):163 -171WU Yican,HUANG Qunying,ZHU Zhiqiang,et al.Progress in design and development of series liquid lithium-lead experimental loops in China[J].Nuclear Science and Engineering,2009,29(2):163-171
17 Hu L,Wu Y.Probabilistic safety assessment of the dual-cooled waste transmutation blanket for the FDS-I[J].Fusion Engineering and Design,2006,81(8-14):1403-1407
18 Wu Y,FDS Team.Conceptual design of the China fusion power plant FDS-II[J].Fusion Engineering and Design,2008,83(10-12):1683-1689
19 盛美玲.铅合金冷却反应堆非能动余热排出系统优化设计研究[D].合肥:中国科学技术大学,2013SHENG Meiling.Optimal design and study of passive decay heat removal system for lead alloy cooled reactor[D].Hefei:University of Science and Technology of China,2013
20 Wu Y,FDS Team.Conceptual design activities of FDS series fusion power plants in China[J].Fusion Engineering and Design,2006,81(23-24):2713-2718
21 Wu Y.Progress in fusion-driven hybrid system studies in China[J].Fusion Engineering and Design,2002,63-64(1):73-80
22 Wu Y,FDS Team.Design analysis of the China Dual-Functional Lithium Lead(DFLL)test blanket module in ITER[J].Fusion Engineering and Design,2007,82(1):1893-1903
23 盛美玲,金鸣,柏云清,等.中国铅合金冷却研究堆事故余热排出系统概念设计与分析[J].核科学与工程,2014,34(1):91-96SHENG Meiling,JIN Ming,BAI Yunqing,et al.Preliminary design and analysis of emergency decay heat removal system for China lead alloy cooled research reactor[J].Nuclear Science and Engineering,2014,34(1):91-96
24 Ye C,Zheng M G,Wang Y,et al.Study on the long-term passive cooling extension of AP1000 reactor[J].Nuclear Science and Techniques,2013,24(4):040601
25 Cao R F,Wu Y C,Pei X,et al.Multi-objective optimization of inverse planning for accurate radiotherapy[J].Chinese Physics C,2011,35(3):313-317
26 王强龙.加速器驱动次临界堆始发事件及非能动安全特性初步研究[D].合肥:中国科学技术大学,2013,Doi:10 .7666/d.Y2354113WANG Qianglong.Preliminary research on initial events and passive safety characteristics of accelerator driven system-reactor[D].Hefei:University of Science and Technology of China,2013,Doi:10.7666/d.Y2354113
27 蔡琦,郁军,金家善,等.核动力装置运行过程可靠性研究现状与发展[J].核技术,2002,25(3):235-240CAI Qi,YU Jun,JIN Jiashan,et al.Current situation and development on reliability analysis of operation process in the nuclear power plant[J].Nuclear Techniques,2002,25(3):235-240
28 田雨,雷晓辉,蒋云钟,等.水文模型参数敏感性分析方法研究评述[J].水文,2010,30(4):9-12+62TIAN Yu,LEI Xiaohui,JIANG Yunzhong,et al.Comment on parameter sensitivity analysis of hydrological model[J].Journal of China Hydrology,2010,30 (4):9-12+62