Unstructured Grids and the Multigroup Neutron Diffusion Equation
Author
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2013, Issue 2013 (31 Dec. 2013), pp.1-26, 26 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2013-08-27
Country of Publication
Egypt
No. of Pages
26
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
The neutron diffusion equation is often used to perform core-level neutronic calculations.
It consists of a set of second-order partial differential equations over the spatial coordinates that are, both in the academia and in the industry, usually solved by discretizing the neutron leakage term using a structured grid.
This work introduces the alternatives that unstructured grids can provide to aid the engineers to solve the neutron diffusion problem and gives a brief overview of the variety of possibilities they offer.
It is by understanding the basic mathematics that lie beneath the equations that model real physical systems; better technical decisions can be made.
It is in this spirit that this paper is written, giving a first introduction to the basic concepts which can be incorporated into core-level neutron flux computations.
A simple two-dimensional homogeneous circular reactor is solved using a coarse unstructured grid in order to illustrate some basic differences between the finite volumes and the finite elements method.
Also, the classic 2D IAEA PWR benchmark problem is solved for eighty combinations of symmetries, meshing algorithms, basic geometric entities, discretization schemes, and characteristic grid lengths, giving even more insight into the peculiarities that arise when solving the neutron diffusion equation using unstructured grids.
American Psychological Association (APA)
Theler, Germán. 2013. Unstructured Grids and the Multigroup Neutron Diffusion Equation. Science and Technology of Nuclear Installations،Vol. 2013, no. 2013, pp.1-26.
https://search.emarefa.net/detail/BIM-487552
Modern Language Association (MLA)
Theler, Germán. Unstructured Grids and the Multigroup Neutron Diffusion Equation. Science and Technology of Nuclear Installations No. 2013 (2013), pp.1-26.
https://search.emarefa.net/detail/BIM-487552
American Medical Association (AMA)
Theler, Germán. Unstructured Grids and the Multigroup Neutron Diffusion Equation. Science and Technology of Nuclear Installations. 2013. Vol. 2013, no. 2013, pp.1-26.
https://search.emarefa.net/detail/BIM-487552
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-487552