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

2017 ◽  
Vol 2017 ◽  
pp. 1-11 ◽  
Author(s):  
Yixue Chen ◽  
Bin Zhang ◽  
Liang Zhang ◽  
Junxiao Zheng ◽  
Ying Zheng ◽  
...  
Keyword(s):  
Anisotropic Scattering ◽  
Radiation Shielding ◽  
Discrete Ordinates ◽  
Boltzmann Transport ◽  
Reactor Physics ◽  
Linear System Of Equations ◽  
Diffusion Synthetic Acceleration ◽  
Transport Code ◽  
Discontinuous Finite Element ◽  
Solution Methods

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.

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

2017 ◽  
Vol 2017 ◽  
pp. 1-5
Author(s):  
Bin Zhang ◽  
Liang Zhang ◽  
Yixue Chen
Keyword(s):  
Experimental Data ◽  
Anisotropic Scattering ◽  
Radiation Shielding ◽  
Discrete Ordinates ◽  
Reactor Physics ◽  
Transport Code ◽  
Ion Accelerator ◽  
Continuum Energy ◽  
Direct Measurements ◽  
Good Agreement

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. To validate the applicability of the code to accelerator shielding problems, ARES is adopted to simulate a series of accelerator shielding experiments for 43 MeV proton-7Li quasi-monoenergetic neutrons, which is performed at Takasaki Ion Accelerator for Advanced Radiation Application. These experiments on iron and concrete were analyzed using the ARES code with FENDL/MG-3.0 multigroup libraries and compared to direct measurements from the BC501A detector. The simulations show good agreement with the experimental data. The ratios of calculated values to experimental data for integrated neutron flux at peak and continuum energy regions are within 64% and 25% discrepancy for the concrete and iron experiments, respectively. The results demonstrate the accuracy and efficiency of ARES code for accelerator shielding calculation.

Verification for Ray Effects Elimination Module of Radiation Shielding Code ARES by Kobayashi Benchmarks

2014 ◽  
Author(s):  
Mengteng Chen ◽  
Bin Zhang ◽  
Yixue Chen
Keyword(s):  
Radiation Transport ◽  
Source Region ◽  
Anisotropic Scattering ◽  
Relative Difference ◽  
Radiation Shielding ◽  
Benchmark Problems ◽  
Discrete Ordinates ◽  
Ray Effects ◽  
Good Agreement

ARES is a multi-group of anisotropic scattering transport shielding code based on discrete ordinates method. The 3D radiation transport benchmark problems proposed by Kobayashi were calculated by ARES with sub-module ARES_RayEffect which using first collision method for ray effects mitigation. ARES_RayEffect calculates uncollided flux and first collision source moments for ARES. The uncollided flux is obtained by a ray tracing calculation between a source point and a target mesh center. In addition, ARES_RayEffect has a modifying factor function to improve the quality of uncollided flux calculation. For verification, the results of MCNP code are used as reference solution and the results of TORT with FNSUNCL3 are compared. ARES_RayEffect introduced the modifying factor to reduce the relative difference of meshes near the source region. For example, at the position (15,15,15) in Problem 1 case i, the relative difference of the result of ARES with ARES_RayEffect is −2.34%, while relative difference of the result of TORT with FNSUNCL3 is −11.92%. The calculated total neutron fluxes show good agreement with the MCNP solutions. For the pure absorber cases, the maximum differences are less than 3%. For the half scattering cases, the maximum differences are less than 11%. Numerical results demonstrate that ray effects can be effectively mitigated.

Tripoli-4 Gamma-Ray Dose Calculation for Spent PWR Fuels

2013 ◽  
Author(s):  
Yi-Kang Lee ◽  
Kabir Sharma
Keyword(s):  
Gamma Ray ◽  
Dose Calculation ◽  
Radiation Shielding ◽  
Pressurized Water Reactor ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Heterogeneous Model ◽  
Transport Code ◽  
Fuel Pin ◽  
Monte Carlo Transport

The gamma-ray dose calculation is essential for the radiation shielding of pressurized water reactor (PWR) spent fuels. Homogenization modeling of fuel pin lattices for typical PWR spent fuel pins is regularly applied on the radiation protection calculation of gamma-ray dose in an air medium. However, depending on the size of the homogenized lattice and the location of the detectors, under-estimation or over-estimation of the gamma-ray dose due to the homogenization modeling can be obtained with respect to the detailed heterogeneous model. In previous published results from MCNP-4A and 4C calculations on gamma-ray dose from spent PWR fuel pins, very different homogeneous to heterogeneous (Hom/Het) ratios were reported. In this study these Hom/Het ratios have been re-evaluated and benchmarked by using the TRIPOLI-4 Monte Carlo transport code. The new TRIPOLI-4 mesh tally capabilities have also been applied to calculate the radial and axial gamma-ray dose distribution. With the recently upgraded TRIPOLI-4 display tool, the dose rate maps and the isodose rate curves around a spent PWR fuel assembly have been established.

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