摘要
针对核燃料循环系统中不同物理形态的核燃料,建立相应的中子动力学—热工水力耦合模型,开发了用于固体、溶液、粉末、核燃料系统临界事故源项计算的程序GETAC-2.0.利用国际上公开的基准实验数据对程序进行了验证,程序对功率(裂变率)峰值的计算结果与基准实验数据的相对误差在12%以内,验证了GETAC-2.0程序的准确性.
Based on individual neutronic-kinetics and thermal-hydraulics coupling model of nuclear fuel with different physical forms,GETAC-2.0 code was developed for source term calculation of solid,solution and powder fuel in the nuclear fuel cycle system when criticality accidents happened.The relative error of the peak power（ fission rate） calculated by GETAC-2.0 code is 12% compared with the benchmark experimental data,which verifies the accuracy of the code.
作者
朱庆福
张驰
夏兆东
ZHU Qingfu;ZHANG Chi;XIA Zhaodong(China Institute of Atomic Energy,Beijing 102413,China)
出处
《南华大学学报（自然科学版）》
2018年第3期1-7,共7页
Journal of University of South China：Science and Technology
基金
国家科技重大专项项目:先进乏燃料贮存技术研究(2015ZX06004002)
