摘要
在10MW球床式高温气冷实验堆(HTR-10)首次临界前,达到首次临界的堆芯燃料球装量预估是物理设计的一项重要任务。为了确保物理设计的可靠性,引入蒙特卡罗程序MCNP对VSOP程序的计算结果进行校验。根据HTR-10的特点对燃料元件和堆结构,设计出近似而合理的MCNP描述;再选择合理的计算特征值问题的参数,包括跳过的周期数、每周期标定的源数目和得到特征值的周期数;研究燃料球结构的不同描述对keff的影响;确定较优的计算方案。该方案的计算结果表明,在27℃、空气气氛下,MCNP和VSOP程序预估的达到首次临界的总球数分别为16864个和16821个,相对误差为0.25%。HTR-10的首次临界实验表明,预估与实验的结果相对误差小于1.0%。
Before the 10 MW pebble-bed High Temperature Gas-cooled Reactor-Test Module (HTR-10) reached the first criticality, the prediction calculations of the fuel loading of the core was a main physics design concern. In order to ensure the reliability of the physics design, verification calculations with Monte Carlo code MCNP has been carried out. Firstly, the sophisticated structure of the fuel element and reactor were described approximately and rationally, based on the HTR-10 characteristics. Then, the parameters of the eigenvalue calculation were chosen rationally, including number of cycles to be skipped before beginning, nominal source size per cycle, and number of cycles for calculation of eigenvalue; and the effect of different descriptions for HTR-10 fuel element structure was studied. Finally, the better scheme was determined. The results of the scheme showed that under the atmosphere of air with a temperature of 27°C, the results of prediction calculation for the number of spheres including the fuel elements and the graphite elements, using MCNP and VSOP, were 16864 and 16821, respectively, with a relative error of 0.25%. According to the results of the first criticality of HTR-10, the experimental and predicted results were agreed well with low relative error less than 1%.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2005年第1期28-34,共7页
Nuclear Power Engineering
基金
国家"863"计划重点能源项目
关键词
球床式高温气冷堆
首次临界
装料
VSOP程序
MCNP程序
Computer software
Eigenvalues and eigenfunctions
Experimental reactors
High temperature reactors
Monte Carlo methods
Nuclear fuel elements
