Development and preliminary verification of 2-D transport module of radiation shielding code ARES
- 1. School of Nuclear Science and Engineering, North China Electric Power University, Beijing (China)
Description
The 2-D transport module of radiation shielding code ARES is two-dimensional neutron and radiation shielding code. The theory model was based on the first-order steady state neutron transport equation, adopting the discrete ordinates method to disperse direction variables. Then a set of differential equations can be obtained and solved with the source iteration method. The 2-D transport module of ARES was capable of calculating keff and fixed source problem with isotropic or anisotropic scattering in x-y geometry. The theoretical model was briefly introduced and series of benchmark problems were verified in this paper. Compared with the results given by the benchmark, the maximum relative deviation of keff is 0.09% and the average relative deviation of flux density is about 0.60% in the BWR cells benchmark problem. As for the fixed source problem with isotropic and anisotropic scattering, the results of the 2-D transport module of ARES conform with DORT very well. These numerical results of benchmark problems preliminarily demonstrate that the development process of the 2-D transport module of ARES is right and it is able to provide high precision result. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 47
- Journal Issue
- suppl
- Journal Page Range
- p. 494-498
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48069049
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCURACY; ANISOTROPY; BENCHMARKS; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED CONTROL SYSTEMS; DIFFERENTIAL EQUATIONS; DISCRETE ORDINATE METHOD; FLUX DENSITY; GEOMETRY; NEUTRON TRANSPORT; SCATTERING; SHIELDING; STEADY-STATE CONDITIONS; TWO-DIMENSIONAL CALCULATIONS; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; EQUATIONS; EVALUATION; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; POWER REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 figs., 3 tabs., 7 refs.