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.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1994年第2期146-151,共6页
Nuclear Power Engineering
关键词
快堆
中子截面
铅冷却剂
物理性能
Fast reactor Lead Physics property Neutron cross section