考虑瞬态分析的反应堆结构关键间隙优化设计
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摘要
反应堆堆内关键间隙设计是反应堆堆内构件结构设计的关键内容。分析了影响堆内构件与压力容器间间隙值的影响因素,针对三种典型间隙,基于通用有限元软件ANSYS,研究了瞬态工况下反应堆内关键间隙变化,提出了一种新的反应堆内关键间隙优化设计方法。研究成果已成功应用于三代核电华龙一号反应堆内关键间隙的优化设计中,有效提高了反应堆内关键间隙设计的合理性和可靠性。
Design of reactor structure key clearances is the important part in the reactor internals structure design. This paper analyzed the influence factors on clearance value between reactor internals and pressure vessel. Then,the variations of the reactor structure key clearances under transient conditions had been investigated by using the general finite element analysis software,ANSYS. A new kind of design method of the reactor structure key clearances was offered. The investigation result has successfully been used to the reactor structure key clearances optimum design of HUALONG 1 which is the three-generation advanced nuclear power reactor. The design has reliability and rationality for that the design of reactor structure key clearance has been improved effectively.
Design of reactor structure key clearances is the important part in the reactor internals structure design. This paper analyzed the influence factors on clearance value between reactor internals and pressure vessel. Then,the variations of the reactor structure key clearances under transient conditions had been investigated by using the general finite element analysis software,ANSYS. A new kind of design method of the reactor structure key clearances was offered. The investigation result has successfully been used to the reactor structure key clearances optimum design of HUALONG 1 which is the three-generation advanced nuclear power reactor. The design has reliability and rationality for that the design of reactor structure key clearance has been improved effectively.
引文
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[11]左巧林,秋穗正,王明军.恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究[J].原子能科学技术,2016,50(05):829-834.
[12]张丽屏,杜娟,刘文进.反应堆压力容器接管三维有限元分析[J].东方电气评论,2012,26(4):62-67.
[13]徐芝纶.弹性力学[M].北京:高等教育出版社,2006.
[2]张翟.压紧弹性环的设计方案优化分析[C]//第17届全国反应堆结构力学会议论文集.出版地不详:[出版单位不详],2012.
[3]黄磊,丁宗华.CAP1400堆内构件压紧弹性环的优化设计[J].机械工程师,2015(6):123-125.
[4]邬国伟.核反应堆工程设计[M].北京:原子能出版社,1997.
[5]孙中宁.核动力设备[M].哈尔滨:哈尔滨工程大学出版社,2003.
[6]赵兆颐,朱瑞安.反应堆热工流体力学[M].北京:清华大学出版社,1992.
[7]姚伟达,谢永诚.模态叠加法在解间隙动力问题中的应用[C]//全国反应堆结构力学会议论文集.出版地不详:[出版单位不详],1998.
[8]于雷,关欣.反应堆压力容器与堆内构件接管的热态间隙计算[J].科技创新与应用,2015(15):101-101.
[9]段孟强,陈五星,季晨龙.压水堆一回路系统热工水力稳态计算模型的建立[J].四川兵工学报,2013,34(12):132-134.
[10]刘家磊,蔡琦,张杨伟,等.稳压器在船用核反应堆舱室散热的模拟研究[J].四川兵工学报,2013,34(11):48-51.
[11]左巧林,秋穗正,王明军.恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究[J].原子能科学技术,2016,50(05):829-834.
[12]张丽屏,杜娟,刘文进.反应堆压力容器接管三维有限元分析[J].东方电气评论,2012,26(4):62-67.
[13]徐芝纶.弹性力学[M].北京:高等教育出版社,2006.