Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method
Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method
复制标题
使用矢量化蒙特卡罗方法进行燃料组装的中子分析代码
DOI:
10.13182/nse89-a23688
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发表时间:
1989
影响因子:
1.2
通讯作者:
M. Aoyama
中科院分区:
文献类型:
--
作者:
Y. Morimoto;Hiromi Maruyama;K. Ishii;M. Aoyama
AbstractA fuel assembly analysis code, VMONT, in which a multigroup neutron transport calculation is combined with a burnup calculation, has been developed for comprehensive design work use. The neutron transport calculation is performed with a vectorized Monte Carlo method that can realize speeds >10 times faster than those of a scalar Monte Carlo method. The validity of the VMONT code is shown through test calculations against continuous energy Monte Carlo calculations and the PROTEUS tight lattice experiment.