加速器驱动10 MW快热耦合气冷堆物理方案研究

Study of Physical Scheme for 10 MW Accelerator-driven Fast-thermal Coupled Gas-cooled Reactor

  • 摘要: 加速器驱动的次临界系统(ADS)在实现嬗变核废料方面具有良好的前景。对加速器驱动10 MW次临界快热耦合能谱气冷堆的物理方案进行了设计和研究,利用MCNPX和ORIGEN耦合的计算程序COUPLE2.0对该方案进行了计算,其中,中子截面采用ENDF-7处理后得到的5个温度300、600、900、1500、2500 K下的连续能量核数据库。得到该方案350 d燃耗期间的keff、质子效率、缓发中子份额以及加速器束流强度的变化。进而计算得到了该方案的燃耗信息,并分析了该方案的嬗变能力。结果表明,该方案在350 d燃耗期间的keff、加速器束流强度变化较小,嬗变支持比为24.86,具有较好的嬗变效果。

     

    Abstract: The accelerator-driven sub-critical system has promising future in transmutation of nuclear spent fuels. A physical design of a 10 MW fast-thermal spectrum gas-cooled reactor was studied. The program COUPLE2.0, which couples with MCNPX and ORIGEN, was applied to compute this scheme, and the continuous energy neutron cross section was obtained by the nuclear data library of ENDF-7 which was modified with five different temperatures: 300, 600, 900, 1500, and 2500 K. The physical parameters such as keff, proton efficiency, delayed neutron fraction and accelerator current varying with the burnup time were obtained. The system during 350 d burnup was obtained and the transmutation capability was analyzed by the further calculation. It is found that during the 350 d burnup, the variations of keff and accelerator current are relatively small. The system has good transmutation capability with the transmutation support ratio of 24.86.

     

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