HTR-10初次临界装料预估  

Prediction calculation of HTR-10 fuel loading for the first criticality

作　　者：经荥清[1] 杨永伟[1] 古玉祥[1] 单文志[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2001年第4期116-119,共4页Journal of Tsinghua University(Science and Technology)

基　　金：国家"八六三"高技术项目! (86 3-6 14 -0 2

摘　　要：10 MW高温气冷实验堆 (简称 HTR- 10 )在清华大学核能技术设计研究院建成 ,并于 2 0 0 0年 12月实现了初次临界。该文利用高温气冷堆物理模拟程序 VSOP对 HTR- 10初次临界装料进行预估 ,计算了初次临界所需燃料球和石墨球数 ,为临界实验提供依据。在计算中考虑了燃料元件的双重非均匀性、谱计算中的曲率反馈和石墨球与燃料球均匀混合的效应以及堆芯顶空腔附近扩散系数的输运修正。还详细考虑了堆芯燃料球和石墨球以及反射层石墨中杂质对反应性的影响。初次临界实验表明 ,临界装料的预估值与试验结果相对误差在 1%之内 。The 10MW high temperature gas cooled reactor (HTR 10) was built at Institute of Nuclear Energy Technology, Tsinghua University, and the first criticality was attained in Dec. 2000. The high temperature gas cooled reactor physics simulation code VSOP was used for the prediction of the fuel loading for HTR 10 first criticality. The number of fuel element and graphite element was predicted to provide reference for the first criticality experiment. The prediction calculations toke into account the factors including the double heterogeneity of the fuel element, buckling feedback for the spectrum calculation, the effect of the mixture of the graphite and the fuel element, and the correction of the diffusion coefficients near the upper cavity based on the transport theory. The effects of impurities in the fuel and the graphite element in the core and those in the reflector graphite on the reactivity of the reactor were considered in detail. The first criticality experiment showed that the predicted values and the experiment results were in good agreement with little relative error less than 1%, which means the prediction was successful.

关 键 词：HTR-10 球床式高温气冷堆 燃料球 初次临界 石墨球 堆芯燃料 装料 

分 类 号：TL424.26[核科学技术—核技术及应用]