摘要
Th-^(233)U热中子增殖堆是一种尚末问世的第二代原子核反应堆。本文用热中子的物理参数并以钍在堆中衍生的^(233)U达到饱和值时作为堆燃料的更换周期,探讨了此类堆所具有的物理特性。初步结果表明:此类堆具有:1)钍的高耗损率;2)高的中子通量运行较为有利;3)进堆的^(233)U含量应尽可能低些;4)有着较深的燃耗等物理特性。
The thorium uranium-233 thermal-neutron breeder reactor is a conceptive and perspec-ive reactor. In this article the well established thermal-neutron cross-sections are employed study the consumption of thorium and the generation of 233U, in order to better unders-and the physical properties of such reactor. Upon the assumption that the period of uel changing is not shorter than the time for the induced 233U to reach its saturation toncentration, it turns out that the reactor apparently possesses the physical properties: 1, high thorium consumptivity, 2. high neutron flux operation preferable; 3. low input 233U-Th ratio and 4. high fuel burn-up.
出处
《核技术》
CAS
CSCD
北大核心
1991年第12期705-711,共7页
Nuclear Techniques
关键词
热中子增殖堆
积分中子通量
燃耗
Th-233U breeder reactor Integral neutron fluxThorium consumptivity 233U saturation concentrationBurn-up
