Development of a polynomial nodal model to the multigroup transport equation in one dimension
Thesis/Dissertation
·
OSTI ID:5234454
A polynomial nodal model that uses Legendre polynomial expansions was developed for the multigroup transport equation in one dimension. The development depends upon the least-squares minimization of the residuals using the approximate functions over the node. Analytical expressions were developed for the polynomial coefficients. The odd moments of the angular neutron flux over the half ranges were used at the internal interfaces, and the Marshak boundary condition was used at the external boundaries. Sample problems with fine-mesh finite-difference solutions of the diffusion and transport equations were used for comparison with the model.
- Research Organization:
- Iowa State Univ. of Science and Technology, Ames (USA)
- OSTI ID:
- 5234454
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANGULAR DISTRIBUTION
BOUNDARY CONDITIONS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
EQUATIONS
FINITE DIFFERENCE METHOD
FUNCTIONS
ITERATIVE METHODS
MARSHAK BOUNDARY CONDITIONS
MATHEMATICAL MODELS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
POLYNOMIALS
RADIATION FLUX
TRANSPORT THEORY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANGULAR DISTRIBUTION
BOUNDARY CONDITIONS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
EQUATIONS
FINITE DIFFERENCE METHOD
FUNCTIONS
ITERATIVE METHODS
MARSHAK BOUNDARY CONDITIONS
MATHEMATICAL MODELS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
POLYNOMIALS
RADIATION FLUX
TRANSPORT THEORY