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基于高精度子通道程序的CHF关系式开发研究

Study on CHF Relational Expression Development Based on High-precision Subchannel Code
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摘要 采用非均匀加热典型栅元和导向管栅元三组临界热流密度(CHF)试验数据,利用高精度子通道分析软件ATHAS获得局部参数,完成适用于燃料组件偏离泡核沸腾比(DNBR)分析的CHF关系式开发,得到导向管冷壁效应因子和DNBR限值;并与采用FLICA软件开发的关系式结果进行对比,结果表明,ATHAS软件开发的关系式计算得到的DNBR限值更低,且对烧毁(BO)点轴向位置和CHF的预测率更高。 Three groups of CHF test data of non-uniform heating typical grid and guide tube grid were adopted,and the local parameters were obtained by using high precision subchannel code ATHAS.The development of CHF relation suitable for the analysis of fuel assembly deviation from nucleate boiling ratio(DNBR)was completed,and the cold wall effect factor and DNBR limit of guide tube were obtained.Compared with the results of the correlation developed by FLICA,the DNBR limit calculated by the relationship developed by ATHAS is lower,and the prediction rate of axial position of burn-out(BO)point and CHF is higher.
作者 吴长娥 张玉相 陈昌义 蒋理 单建强 傅先刚 Wu Change;Zhang Yuxiang;Chen Changyi;Jiang Li;Shan Jianqiang;Fu Xiangang(Nuclear Fuel and Materials Department,China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen,Guangdong,518000;School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an,710049,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2024年第4期45-52,共8页 Nuclear Power Engineering
基金 国家重点研发计划项目(2018YFB1900403)。
关键词 ATHAS软件 临界热流密度(CHF) 偏离泡核沸腾比(DNBR) ATHAS code Critical Heat Flux(CHF) Departure from nucleate boiling ratio(DNBR)
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