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石墨一熔盐零功率堆若干物理参量的模拟
Calculation of some physical parameters of graphite-molten zero power reactor
【Author】 XIE Qin~(1,2),TANG Xiao-bin~2,GENG Chang-ran~2,YAO Ze-en~1 (1.Nuclear Scinence and Technology Division,Lanzhou University,Lanzhou of Gansu Prov.730000,China; 2.Nuclear Science and Engineering Department,Nanjing University of Aeronautics and Astronautics,Nanjing of Jiangsu Prov.210016,China)
【机构】 兰州大学核科学与技术学院; 南京航空航天大学核科学与工程系;
【摘要】 作为获国际认可的第四代核电站反应堆堆型之一的熔盐堆,具有固有安全性高、经济性好、核资源可持续发展以及易于防止核扩散等优点。针对石墨熔盐零功率堆的几何参数,利用蒙特卡罗计算程序MCNP5建立了物理计算模型,计算临界情况下堆芯径向、轴向中子通量及增殖区厚度与Th-U转换比CR的关系。结果表明,1)石墨—熔盐零功率堆堆芯中子通量密度分布较为平坦;2)石墨熔盐零功率堆反射层厚度和增殖区厚度在一定范围内,转换比CR随反射层厚度或增殖区厚度的增加而增加,当超出该范围,转换比CR不再随反射层厚度或增殖区厚度的增加而明显增加。
【Abstract】 The molten salt reactor(MSR) is the only one liquid-fuel reactor in six candidates of GenerationⅣadvanced nuclear reactor,which is characterized by remarkable advantages in safety,economics and sustainable development of the fissile resource and proliferation resistance of nuclear energy.In this paper has set up a detailed computational model using the Monte Carlo code MCNP5.Then a detailed study about radical/axis neutron flux and the influences of the reflect thickness or blanket thickness in the conversion ration(CR) on the Th-U fuel cycle.Main results obtained in this calculation show that(1) The neutron flux distribution of the graphite-molten zero power reactor core is relatively smooth;(2) The convert ratio will increases in a certain degree with the thickness of reflector and/or the thickness of breeding region and when it exceed this degree the convert ratio cannot get increased significantly.
【Key words】 Molten salt reactor; Monte Carlo Method; MCNP; Neutron flux;
- 【会议录名称】 中国核科学技术进展报告(第二卷)——中国核学会2011年学术年会论文集第3册(核能动力分卷(下))
- 【会议名称】中国核学会2011年学术年会
- 【会议时间】2011-10-11
- 【会议地点】中国贵州贵阳
- 【分类号】TL426
- 【主办单位】中国核学会