Published 2013
| Version v1
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Nodal deterministic simulation for problems of neutron shielding in multigroup formulation
Creators
- 1. Universidade do Estado do Rio de Janeiro (UERJ), Rio de Janeiro, RJ (Brazil). Dept. de Modelagem Computacional
Description
In this paper, we propose the use of some computational tools, with the implementation of numerical methods SGF (Spectral Green's Function), making use of a deterministic model of transport of neutral particles in the study and analysis of a known and simplified problem of nuclear engineering, known in the literature as a problem of neutron shielding, considering the model with two energy groups. These simulations are performed in MatLab platform, version 7.0, and are presented and developed with the help of a Computer Simulator providing a friendly computer application for their utilities
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45097250.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Simulacao deterministica nodal para problemas de blindagem de neutrons na formulacao multigrupo
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- INIS-BR--14524
Conference
- Title
- international nuclear atlantic conference
- Acronym
- INAC 2013
- Dates
- 24-29 Nov 2013
- Place
- Recife, PE (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 45097250
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DETERMINISTIC ESTIMATION; DISCRETE ORDINATE METHOD; GREEN FUNCTION; NEUTRON TRANSPORT THEORY; NEUTRONS; NODAL EXPANSION METHOD; SHIELDING
- Descriptors DEC
- BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; FERMIONS; FUNCTIONS; HADRONS; NUCLEONS; SIMULATION; TRANSPORT THEORY
Optional Information
- Notes
- 14 refs., 7 figs., 1 tab.