对先进核能系统中U-Pu循环的研究

Study of U-Pu Cycle in Advance Nuclear Power System

摘要: 利用新开发的数据库和程序对加速器驱动的次临界反应堆中的Ｕ－Ｐｕ循环进行了详细的理论研究．通过对反应堆功率、临界系数、γ和中子通量以及裂变核的演化等计算，得到了令人满意的中子学结果.The U-Pu cycle in accelerator driven subcritical reactor is studied by means of new data library and code. The satisfactory neutronics results are obtained by calculating the reactor power, critical value, gamma and neutron flux and evolution of fissioning nuclear density. The detailed analysis is also presented.

Abstract: The U-Pu cycle in accelerator driven subcritical reactor is studied by means of new data library and code. The satisfactory neutronics results are obtained by calculating the reactor power, critical value, gamma and neutron flux and evolution of fissioning nuclear density. The detailed analysis is also presented.