铀-钚-锆燃料合金物性模型  

MODELING OF PHYSICAL PROPERTIES FOR U-Pu-Zr FUEL ALLOYS

作　　者：李文埮[1] 谢国强[1] 

机构地区：[1]中国原子能科学研究院

出　　处：《原子能科学技术》1991年第5期66-72,共7页Atomic Energy Science and Technology

摘　　要：文章用最小二乘法对数据的直接数学拟合或确定物理表式常数两种方法建立了铀-钚-锆燃料合金的物性模型,变量为组成和温度。物性包括密度、固相线(液相线)温度、热膨胀、比热容和热导率。在置信度为95%时,模型的不确定度分别为±0.5%,±5.7%,±5.5%,±5.0%和±9.7%。这些模型也适用于铀-锆合金。Five physical properties correlations are developed as functions of temperatureand local composition for FBR fuel--U--Pu--Zr alloy. The properties of interestinclude RT theoretical density, solidus (liquidus) temperature, thermal expansion,specific heat capacity and thermal conductivity. The uncertainties in models areestimated to be 0.5%, 5.7% , 5.5%, 5.0% and 9.7% respectively for the 95%confidence limit. These models are also suitable to U--Zr alloy also.

关 键 词：铀 钚 锆 合金 燃料 物性模型 

分 类 号：TL341[核科学技术—核技术及应用]