【作者】 罗娟； 王月英； 罗家成； 李朋洲； 孙磊；

【Author】 LUO Juan;WANG Yue-ying;LUO Jia-cheng;LI Peng-zhou;SUN Lei;Nuclear Power Institute of China;China Institute of Atomic Energy;

【机构】 中国核动力研究设计院； 中国原子能科学研究院；

【摘要】 新型反应堆冷却剂出口温度的大力提升亟须对反应堆回路管道的高温性能进行研究。文章对新型反应堆管道常用材料304类不锈钢、316类不锈钢和改进型9Cr-1Mo钢(又称91钢、T91钢、P91钢)的高温力学性能的标准数据和文献数据进行了分析,比较了三种材料的化学成分、高温拉伸性能和蠕变性能。结果表明,规范规定的91钢的高温拉伸强度基本高于304和316类不锈钢,高温蠕变强度低于316类不锈钢,高于304类不锈钢。研究结果可为第四代新型反应堆(如超临界水冷堆、钠冷快堆、铅冷快堆)以及其他先进反应堆(如行波堆等)的管道结构设计和材料选择提供参考依据。更多还原

【Abstract】 With the increase of coolant outlet temperature in advanced nuclear reactors,it is necessary to study the elevated temperature property of the loop piping material.In this paper,the elevated temperature mechanical property of three common materials used in advanced reactor,i.e.,type 304 stainless steel,type 316 stainless steel and modified 9 Cr-lMo steel(grade 91,T91,P91 steel),have been researched based on standards and literatures.The chemical composition,tensile and creep property of the three kinds of materials at elevated temperature has been investigated.Results show that the tensile strength of grade 91 steel is basically higher than that of type 304 and316 stainless steel at elevated temperature,while its creep strength is lower than type 316 stainless steel,but higher than type 304 stainless steel.The research results can provide some reference for the choice of loop piping material for generation Ⅳ reactors(e.g.,supercritical water cooled reactor,sodium-cooled fast reactor and lead-cooled fast reactor) and other advanced reactors(e.g.,traveling wave reactor).更多还原