基于ANSYS二次开发的反应堆冷却剂系统LOCA非线性动力分析
|
摘要
利用ANSYS程序进行反应堆冷却剂丧失事故(LOCA)瞬态下的非线性动力响应分析,实现参数化、模块化的高效建模。在此基础上,对ANSYS程序进行二次开发,形成LOCA瞬态动力响应分析用的专用模块。基于ANSYS程序二次开发的LOCA模块的分析结果与专用LOCA分析软件的计算结果基本一致,局部存在一定差异。根据瞬态动力学分析的经验,反应堆冷却剂系统中存在较多非线性因素,该差异在可以接受的范围内。整个计算过程输入格式灵活、建模方便、可视性好、可自动生成报告,可大大提高实际工程分析的效率。
In this paper,nonlinear dynamic response under loss of coolant accident(LOCA) transient in the nuclear reactor coolant system(RCS) is investigated with ANSYS program.Many nonlinear factors,such as different structural stiffness in tension and compression,gap and plastic strain caused by main pipes' break etc.are considered.The Secondary development of ANSYS is performed to form the customized module for implementing effective parameterized and modular modeling and LOCA nonlinear analysis.Comparison of the results calculated by ANSYS and program-specific shows that the results are generally consistent,but there are some differences locally.According to the experience of transient dynamic analysis,and there are so many non-linear factors in the reactor coolant system,the difference is acceptable.The efficiency of this en-gineering analysis is improved remarkably with the convenience of input and modeling,viewable layout and automatic creating of reports,when using the customized module based on ANSYS.
In this paper,nonlinear dynamic response under loss of coolant accident(LOCA) transient in the nuclear reactor coolant system(RCS) is investigated with ANSYS program.Many nonlinear factors,such as different structural stiffness in tension and compression,gap and plastic strain caused by main pipes' break etc.are considered.The Secondary development of ANSYS is performed to form the customized module for implementing effective parameterized and modular modeling and LOCA nonlinear analysis.Comparison of the results calculated by ANSYS and program-specific shows that the results are generally consistent,but there are some differences locally.According to the experience of transient dynamic analysis,and there are so many non-linear factors in the reactor coolant system,the difference is acceptable.The efficiency of this en-gineering analysis is improved remarkably with the convenience of input and modeling,viewable layout and automatic creating of reports,when using the customized module based on ANSYS.
引文
[1]Standard Review Plan[S].U.S.NRC,1997.
[2]Prinja N K,Chitkara N R.Post Collapse Cross sectionalFlattening of Thick Pipes in Plastic Bending[J].NuclEng Des,1984,83:113-121.
[3]Prinja N K,Chitkara N R.Large Rotation,Large StrainAnalysis of Pipe Whip with Flow Choking[J].Nucl EngDes,1986,93:69-81.
[4]Kurihara R.Experimental Studies of42inch Pipe WhipTest under BWR LOCA Conditions[J].Nucl Eng Des,1983,76:23-33.
[5]华云龙,余同希.核电站中管道甩动问题的分析计算方法[J].计算结构力学及其应用,1988,5(1):105-112.
[6]赵国桥.核反应堆管道系统动力响应分析[D].北京:清华大学博士学论文,1992.
[7]余儒宏.反应堆主环路系统抗破裂设计的分析[J].核动力工程,1986,7(6):49-56.
[8]张锡文,何枫,郝鹏飞,等.压水堆主管道破裂工况下的非线性动力响应[J].原子能科学技术,2000,34(5):385-390.
[9]毛庆,曾忠秀,张毅雄,等.反应堆冷却剂系统LOCA非线性动力分析初步研究[C].第十一届全国反应堆结构力学会议,2000.
[10]毛庆.反应堆系统LOCA非线性动力分析.核动力工程[J].1999,20(4):342-347.
[11]毛庆,余红星,肖忠,等.核反应堆地震和失水事故下结构动力分析研究[J].核动力工程,2002,23(1):93-98.
[2]Prinja N K,Chitkara N R.Post Collapse Cross sectionalFlattening of Thick Pipes in Plastic Bending[J].NuclEng Des,1984,83:113-121.
[3]Prinja N K,Chitkara N R.Large Rotation,Large StrainAnalysis of Pipe Whip with Flow Choking[J].Nucl EngDes,1986,93:69-81.
[4]Kurihara R.Experimental Studies of42inch Pipe WhipTest under BWR LOCA Conditions[J].Nucl Eng Des,1983,76:23-33.
[5]华云龙,余同希.核电站中管道甩动问题的分析计算方法[J].计算结构力学及其应用,1988,5(1):105-112.
[6]赵国桥.核反应堆管道系统动力响应分析[D].北京:清华大学博士学论文,1992.
[7]余儒宏.反应堆主环路系统抗破裂设计的分析[J].核动力工程,1986,7(6):49-56.
[8]张锡文,何枫,郝鹏飞,等.压水堆主管道破裂工况下的非线性动力响应[J].原子能科学技术,2000,34(5):385-390.
[9]毛庆,曾忠秀,张毅雄,等.反应堆冷却剂系统LOCA非线性动力分析初步研究[C].第十一届全国反应堆结构力学会议,2000.
[10]毛庆.反应堆系统LOCA非线性动力分析.核动力工程[J].1999,20(4):342-347.
[11]毛庆,余红星,肖忠,等.核反应堆地震和失水事故下结构动力分析研究[J].核动力工程,2002,23(1):93-98.
版权所有：© 2023 中国地质图书馆 中国地质调查局地学文献中心