钍基核燃料的基础研究(英文)

BASIC STUDY ON UTILIZATION OF THORIUM-BASEDNUCLEAR FUEL

一系列ThO_2样品在高通量堆中在不同辐照条件下进行了辐照。在对每个样品进行冷却、溶解后,对^(233)U、^(232)U某些裂片与φ_f、φ_(th)之间的相关性进行了测定。基于这些实验结果,提出了对设计一个Th-U核反应堆可能有用的某些物理参数的范围。即:1.快热中子比,φ_f/φ_(th)<1;2.热中子通量,5×10^(13)<φ_(th)<2.5×10^(14)(n/cm^2);3.钍铀比,1<Th/U<80;4.可裂变燃料与非可裂变燃料之比,0.012<(^(235)U+^(233)U)/(^(238)U+^(232)Th)<0.

Four series of ThO2 samples in pellet form have been irradiated in high flux reactor under various conditions. After cooling and dissolution of each sample separately, the interrelations between 233U, 252U, 235Pa, certain fission fragment nuclides and φf,φth have been determined. Based on these experimental results, the ranges of some physical parameters which might be useful to the design of Th-U nuclear reactor have been presented. Namely, 1. Ratio of fast neutron flux to thermal neutron flux, φf/φth<1; 2. Intensity of thermal neutron flux, 5×1013<φth<2.5×1014(n/cm2); 3. Ratio of thorium to uranium, l<Th/U<80; 4. Ratio of fissionable fuel to non-fissionable fuel, 0.012<(235U+233U)/(238U+232Th)<0.03.