固有安全快堆铅冷却剂及其物理特性  

Lead Coolant of Inherent Safety Fast Peactor and Its Physics Properties

作　　者：赵兆颐[1] 施工[1] 熊平广 贾宝山[1] 胡大璞[1] 

机构地区：[1]清华大学,中国原子能科学研究院

出　　处：《核动力工程》1994年第2期146-151,共6页Nuclear Power Engineering

摘　　要：本文简述了用铅作冷却剂的快中子增殖堆的固有安全性，介绍了铅的热力学性质、输运性质等物理特性；给出了铅的饱和蒸汽压、密度、比热容、比焓、热导率、粘度、普朗特数和热扩散率等特性的较新数据以及作者拟合的铅物性函数关系式；同时，还给出了铅的２５群中子截面数据。The paper describes briefly the inherent safety of a new type fast reactor which uses liquidmetal lead as coolant. Newly published data of thermodynamic and transport properties of leadare collected and presented, including saturation vapour pressure, density, specific heat, specific enthalpy, conductivity, viscosity, Prandtl number and thermal diffusivity. Some curvefitting formulas on lead property data obtained by the authours are introduced. The 25 groupsneutron cross sections of lead are presented also.

关 键 词：快堆 中子截面 铅冷却剂 物理性能 

分 类 号：TL343[核科学技术—核技术及应用]