Solution of the neutron group-diffusion equations by orthogonal collocation with cubic hermite interpolants
Journal Article
·
· Transp. Theory Stat. Phys.; (United States)
The method of orthogonal collocation (OC) is used to find approximate solutions for the neutron group flux and precursor concentration equations of space-time nuclear reactor dynamics. In the OC method, the unknown solution is approximated by a finite linear combination u of local basis functions. The coefficients of this linear combination are determined by forcing the ''defect'', Lu-f, to zero at the Gaussian quadrature abscissae selected as collocation points for maximum accuracy.
- Research Organization:
- Centro de Estudios Nucleares, Universidad Nacional Autonoma dde Mexico, Apdo. Postal 70-543, 04510 Mexico, D. F. Mexico
- OSTI ID:
- 5115226
- Journal Information:
- Transp. Theory Stat. Phys.; (United States), Journal Name: Transp. Theory Stat. Phys.; (United States) Vol. 12:3; ISSN TTSPB
- 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
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALGORITHMS
BOUNDARY CONDITIONS
C CODES
COMPUTER CODES
FINITE DIFFERENCE METHOD
FINITE ELEMENT METHOD
ITERATIVE METHODS
MATHEMATICAL LOGIC
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
RADIATION FLUX
REACTORS
TRANSPORT THEORY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALGORITHMS
BOUNDARY CONDITIONS
C CODES
COMPUTER CODES
FINITE DIFFERENCE METHOD
FINITE ELEMENT METHOD
ITERATIVE METHODS
MATHEMATICAL LOGIC
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
RADIATION FLUX
REACTORS
TRANSPORT THEORY