An International Double-Blind, Peer-Review Journal by NSTRI

Document Type : Research paper

Authors

1 Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran

2 Nuclear Reactor and Safety School, Nuclear Science and Technology Research Institute (NSTRI)

Abstract

Progress in nuclear engineering, as a highly interdisciplinary field, along with evolution in computational software and hardware, gives authorization to 3D transport simulation of highly heterogeneous generation IV reactor cores, instead of 3D diffusion calculation. To improve the computational efficiency of 3D neutron transport, fusion methods(2D/1D) are being considered. These methods offer a lower computational cost compared to the common methods, in which the 3D neutron transport kernel is divided into two separate kernels for each radial and axial direction since the material heterogeneity is not the same in these two directions. In implemented 2D/1D method in this research, the Nodal Diffusion Expansion Method (NEM) is utilized as an axial kernel due to its lower computational cost. Meanwhile, the radial direction was analyzed using the Method of Characteristic (MOC) utilizing modular ray tracing as the transport kernel because of the higher heterogeneity in this direction. The implemented algorithm has been evaluated by simulating the well-known Takeda Model 1 benchmark.

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