300#研究堆安全棒中子注量率计算中的减方差方法对比及应用

Comparison and Application of Variance Reduction Method Employed in Neutron Fluence Rate Calculation for Safety Rod of SPPR-300

  • 摘要: 针对300#研究堆安全棒顶端中子注量率计算中的小体积远距离中子输运问题,采用MCNP减方差方法,通过多次试算与验证计算,对比了各减方差方法在本问题中的适用情况,得到了符合误差要求的计数值。首先,根据本研究堆几何建模模型,选取了点探测器及相关的3种减方差方法进行对比计算,计算结果显示:随着粒子数的增加,计算呈现不稳定现象,未起到减方差的作用。之后,将原有几何模型重新分层建模,并分配适当的栅元重要性,将中子引向目标栅元。按此方法,通过检查中子在各栅元中的径迹及碰撞情况,并增加粒子数计算,得到的计数结果表明:计数相对误差在5%以内,品质因子保持稳定,实现了减方差的目的。

     

    Abstract: When calculating the neutron fluence rate of safety rod in SPRR-300 (swimming pool research reactor), especially the top of safety rod, the problem will occur that neutrons transport in little volume at long distance. Variance reduction techniques used in MCNP were applied to solve the problem. By trial and error, several methods were tested, and efficient variance reduction method for this problem was found. At first, three techniques were chosen to do comparison according to the reactor model. The comparison results showed that an unsteady calculation phenomenon was observed along with the increase of neutron histories. Therefore, this didn’t reduce variance successfully. Then, the reactor model was modified to describe water with multiple cells, so that cell importance could be designated respectively. This variance reduction method induces more neutron tracks into the destination cell. Also, the neutron tracks and collisions in each cell can be checked from the output file. Finally, the calculation results of the updated model show that the relative error is less than 5%, and FOM (figure of merit) is steady, which imply that the variance reduction aim is accomplished.

     

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