用MCNPX计算ADS金属靶散裂中子产额及散裂源中子效率

为了分析加速器驱动系统（ADS）中质子束能量对金属靶散裂产生的中子产额及靶内中子能谱、靶表面的泄漏谱的影响，利用MCNPX对ADS的重金属铅靶、钨靶在不同能量的质子束轰击下的中子产额、中子能谱及靶表面的中子泄漏谱进行了模拟计算，与国际上其他研究机构的模拟结果进行了比较，结果相近.并对铅靶、钨靶的中子产额及泄漏谱进行比较，模拟结果是钨靶的中子产额较铅靶的中子产额大但中子泄漏谱计数较铅的小.结合MCNP5还对一个次临界基准体系中散裂源中子相对于裂变中子的效率进行了计算.

A MCNPX Caculation of the spallation neutron yields from various metal targets and the neutron source efficiency in ADS

In order to analyze the effect of the proton energy on the number of neutrons produced per source proton and the neutron yield spectra and values of neutron leakage distributions per proton over the cylindrical metal target surface in Accelerator Driven System (ADS),MCNPX are used to calculate them under different proton beam energy,and the results are compared with the results of the international organization institutions.The number of neutrons produced per source proton of tungsten target is larger but the tally of neutron leakage is smaller than lead target. Combining the MCNPX with MCNP5,the efficiency of the spallation neutions relative to fission neutrons for a subcritical benchmark system was calculated.