ARES: A Parallel Discrete Ordinates Transport Code for Radiation Shielding Applications and Reactor Physics Analysis

Abstract

ARES is a multidimensional parallel discrete ordinates particle transport code with arbitrary order anisotropic scattering. It can be applied to a wide variety of radiation shielding calculations and reactor physics analysis. ARES uses state-of-the-art solution methods to obtain accurate solutions to the linear Boltzmann transport equation. A multigroup discretization is applied in energy. The code allows multiple spatial discretization schemes and solution methodologies. ARES currently provides diamond difference with or without linear-zero flux fixup, theta weighted, directional theta weighted, exponential directional weighted, and linear discontinuous finite element spatial differencing schemes. Discrete ordinates differencing in angle and spherical harmonics expansion of the scattering source are adopted. First collision source method is used to eliminate or mitigate the ray effects. Traditional source iteration and Krylov iterative method preconditioned with diffusion synthetic acceleration are applied to solve the linear system of equations. ARES uses the Koch-Baker-Alcouffe parallel sweep algorithm to obtain high parallel efficiency. Verification and validation for the ARES transport code system have been done by lots of benchmarks. In this paper, ARES solutions to the HBR-2 benchmark and C5G7 benchmarks are in excellent agreement with published results. Numerical results are presented which demonstrate the accuracy and efficiency of these methods.

Analyses of the TIARA 43 MeV Proton Benchmark Shielding Experiments Using the ARES Transport Code

“…ARES [3,4] is a multidimensional parallel discrete ordinates neutral particle transport code that uses state-ofthe-art methods to obtain accurate solutions to the Boltzmann transport equation. The ARES transport code system consists of seven main modules: DONTRAN1D, DON-TRAN2D, DONTRAN3D, RAY2D, RAY3D, ARES PRE, and ARES POST.…”

Analysis of Spatial Discretization Error Estimators Implemented in ARES Transport Code for SN Equations

“…In this paper, we assess the accuracy of the error estimator implemented in the ARES [12] transport code. The reminder of this paper is organized as follows.…”

An Accurate and Efficient S N Method for Multigroup Neutron Transport Equations in Slab Geometry

“…They can model neutron behavior in complex reactor geometries, calculate criticality, and optimize reactor performance [5,6,7,8]. In neutron shielding design applications, S N methods are used to design neutron shielding materials and configurations to protect workers and the public from radiation exposure [9,10,11]. In medical physics, S N methods are employed for radiation therapy treatment planning.…”