论文信息 - Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method

Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method

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.

K. Ishii | Hiromi Maruyama | Y. Morimoto | M. Aoyama

[1] J. Millot,et al. Preliminary Results of the Feasibility Study on the Convertible Spectral Shift Reactor Concept , 1988 .

[2] R. Chawla,et al. Reactivity and Reaction Rate Ratio Changes with Moderator Voidage in a Light Water High Converter Reactor Lattice , 1984 .

[3] D. R. Harris,et al. MINX: a multigroup interpretation of nuclear X-sections , 1973 .

[4] B. Kuczera,et al. Research and development efforts for the light water high conversion reactor , 1988 .