节点文献
紧密排列棒束燃料组件临界热流密度实验研究
Experimental Study on Critical Heat Flux in Tight Arrangement Fuel Aassembly
【Author】 XIE feng;XU jian-jun;HUANG Yan-ping;YANG Zu-mao;WANG hong-tao;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China;
【机构】 中国核动力研究设计院中核核反应堆热工水力技术重点实验室;
【摘要】 紧密排列堆芯是一种先进的堆芯组件布置技术,堆芯燃料组件采用紧密布置,通过降低堆芯中慢化剂与核燃料的体积比值,有效地减少了堆芯体积和重量,大大提高了铀资源的有效利用率,具有提高堆芯体积功率密度和延长燃耗寿期等优点。紧密排列堆芯燃料组件采用螺旋绕肋定位,且元件间隙很小,是一种新型的堆芯燃料元件结构,其临界热流密度特性与常规棒束堆芯燃料组件存在较大差异,本文针对紧密排列螺旋绕肋棒束堆芯燃料组件,开展堆芯燃料组件临界热流密度(CHF)实验研究,获得了燃料组件不同热工参数下的临界热流密度值以及临界热流密度变化规律。
【Abstract】 The tight arrangement nuclear reactor is one of advanced reactor,in which the fuel assembly is arranged tightly to decrease the volume of reactor core,to increase the conversion ratio,the spiral fin is located around the tight fuel rod,Moreover,the size and the spce of the fuel rod are much smaller,the Thermal hydraulic performance of tight arrangement fuel assembly is different from the conventional rod fuel assemblies,the critical heat flux(CHF) is important for reator research and design,there is no study on CHF of tight arrangement spiral-fin fuel assembly has been carried out in China,Therefore,it is necessary to study the CHF characteristics of the tight arrangement fuel assembly.In this paper,the experimental research of CHF in tight arrangement fuel assembly has been carried out,The CHF of tight arrangement fuel and influence of thermal parameters on the CHF is obtained,The CHF relation of the tight arrangement spiral-fin fuel assembly was obtained based on the test data.
- 【会议录名称】 第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集
- 【会议名称】第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会
- 【会议时间】2017-09-24
- 【会议地点】中国山东荣成
- 【分类号】TL351.1
- 【主办单位】中国核学会核能动力分会反应堆热工流体专业委员会、中核核反应堆热工水力技术重点实验室