Implementation of the decomposition method in domains in AZTRAN
Creators
- 1. IPN, Escuela Superior de Fisica y Matematicas, 07738 Ciudad de Mexico (Mexico)
- 2. ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)
Description
This paper describes the implementation of the decomposition method in domains to the neutron transport code AZTRAN (Aztlan Transport). The code is a tool developed for the AZTLAN platform, which is written in Fortran 90 for the neutron analysis of nuclear reactors. AZTRAN numerically solves the transport equation with time dependence with Cartesian geometry in discrete ordinates. The architecture of computers today allows codes to run in parallel using their components such as processors or GPUs in order to reduce computation time. Because of this, an effort has been made to parallel codes that solve physical models such as the heat or diffusion equation, in which the domain decomposition method has been implemented. The method consists of decomposing the spatial domain into sub-domains, which will be distributed in processors so that each process simultaneously resolves the sub-domain and at the end of approximating the flow in each sub-domain the boundaries are updated. This method was implemented in the stationary two-dimensional version of the AZTRAN code using the message passing interface (Mpi), in which the Benchmark C5/G7-2D was simulated in steady state, which presented encouraging results that motivate a fully version parallel three-dimensional. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares. Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), E-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Additional titles
- Original title (Spanish)
- Implementacion del metodo de descomposicion en dominios en AZTRAN
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 11 p.
Conference
- Title
- peaceful applications of nuclear energy for the Mexico benefit
- Original Conference Title
- 30. Congreso Anual de la SNM: aplicaciones pacificas de la energia nuclear en beneficio de Mexico
- Acronym
- 30. SNM Annual Congress
- Dates
- 4-7 Aug 2019
- Place
- Monterrey, Nuevo Leon (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 51005295
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; COMPUTER ARCHITECTURE; COMPUTERIZED SIMULATION; COMPUTERS; DIFFUSION EQUATIONS; DISCRETE ORDINATE METHOD; FORTRAN; GEOMETRY; HEAT; IMPLEMENTATION; INTERFACES; NEUTRON TRANSPORT; NEUTRONS; REACTORS; STEADY-STATE CONDITIONS; THREE-DIMENSIONAL LATTICES; TIME DEPENDENCE; TRANSPORT THEORY; TWO-DIMENSIONAL SYSTEMS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CRYSTAL LATTICES; CRYSTAL STRUCTURE; DIFFERENTIAL EQUATIONS; ELEMENTARY PARTICLES; ENERGY; EQUATIONS; FERMIONS; HADRONS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; PROGRAMMING LANGUAGES; RADIATION TRANSPORT; SIMULATION