Existing neutronic whole-core simulation codes are problem-oriented. With the
advancement of computer technology and the development of complicated micro-nuclear …

Helical cruciform fuel (HCF) features superior thermal conductivity, high heat transfer area-to-
volume ratio and continual mixing between channels, but its complex radial structure, axial …

In this study, we introduce TARS, a neutron transport code based on the discrete-ordinates
discontinuous finite element (SN-DFEM) method, which tackles existing challenges in the …

The planar method of characteristics (MOC) combined with the coarse-mesh finite difference
(CMFD) method is highly effective for solving the neutron transport equation in pressurized …

This paper focuses on the acceleration of solving fixed-source equations in improved Tone's
method. Since each equation is independent of the other with respect to the energy variable …

Significant accuracy loss has been observed in the MOC/DD method using thin axial
meshes. A theoretical analysis indicates that the accuracy loss results from the deviation in …

The linear axial expansion transport method avoids the negative source problem caused by
transverse leakage in the traditional two-dimensional/one-dimensional (2D/1D) transport …

Abstract The 3D Method of Characteristics (MOC) has high numerical accuracy, geometrical
flexibility, making it suitable for the simulation of advanced reactors with complex geometry …

For better self-shielded cross-section generation in advanced reactor analysis with full-
range spectrum adaptability, the 2-D subassembly calculation capability has been recently …

Gas-cooled microreactors are known for compact designs, high thermal-to-electric
efficiencies, long refueling cycles, and flexible deployment capabilities, representing a …