卧式铅铋堆芯氧化腐蚀特性研究  

Study on Oxidation Corrosion Characteristics of Horizontal Lead-Bismuth Reactor Core

作　　者：陆定晟 王琛[1] 王成龙[1] 岳倪娜 杨平[2] 田文喜[1] 苏光辉[1] 秋穗正[1] Lu Dingsheng;Wang Chen;Wang Chenglong;Yue Nina;Yang Ping;Tian Wenxi;Su Guanghui;Qiu Suizheng(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an,710049,China;Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国核动力研究设计院,成都610213

出　　处：《核动力工程》2023年第3期96-103,共8页Nuclear Power Engineering

基　　金：国家重点研发计划(2019YFB1901300)。

摘　　要：为开展卧式铅铋堆芯氧化腐蚀特性研究,本研究建立液态铅铋氧化腐蚀模型,并基于计算流体动力学方法,运用输运方程源项自定义方法实现耦合计算。研究表明,基准工况下堆芯燃料棒表面氧化层最厚位于出口位置处,中心位置燃料棒表面氧化层厚度显著高于靠近燃料组件盒燃料棒表面氧化层。10000 h后中心位置燃料棒表面仍保持双层氧化层结构,双层氧化层平均总厚度为1.32μm。本研究提出了铅铋堆芯氧化腐蚀特性数值模拟研究方法,能够用于铅铋堆芯氧化腐蚀的预测。In order to study the oxidation corrosion characteristics of horizontal lead-bismuth reactor core,a liquid lead-bismuth oxidation corrosion model was established in this study.Based on computational fluid dynamics method,the self-defined source term method of transport equation was used to realize coupling calculation.The results show that the thickest oxidation layer on the fuel rod surface of the reactor core is located at the outlet position under the reference condition,and the oxidation layer on the fuel rod surface at the center is significantly higher than that near the fuel assembly box.After 10,000 hours,the surface of the fuel rod at the center still maintained a double oxide layer structure,and the average total thickness of the double oxide layer was 1.32μm.This study provides a numerical simulation method for the oxidation corrosion characteristics of leadbismuth reactor cores,which can be used for the prediction of oxidation corrosion of lead-bismuth reactor cores.

关 键 词：铅铋快堆 氧化腐蚀 计算流体动力学(CFD) 

分 类 号：TL334[核科学技术—核技术及应用]