Finite element formulations of nodal schemes for neutron diffusion and transport problems
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5903965
Several finite element formulations of nodal schemes for neutron diffusion problems are presented: They include nonconforming primal formulations as well as mixed and mixed-hybrid ones, with exact or approximate evaluation of the matrix coefficients. These different formulations are compared to one another and also related to well-known point- and mesh-centered finite difference schemes. Some numerical results are given in one and two dimensions with different schemes. Applications to two-dimensional neutron transport problems are also proposed through the general approach of transverse integration.
- Research Organization:
- National Polytechnic Institute, ESFM, Mexico City 07300
- OSTI ID:
- 5903965
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 92:2; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CALCULATIONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FINITE DIFFERENCE METHOD
FINITE ELEMENT METHOD
ITERATIVE METHODS
MATRICES
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
TRANSPORT THEORY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CALCULATIONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FINITE DIFFERENCE METHOD
FINITE ELEMENT METHOD
ITERATIVE METHODS
MATRICES
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
TRANSPORT THEORY