Explicitly interfaced finite element solution of the neutron transport equation
A numerical solution of the first-order, mono-energetic neutron transport equation is found by the finite element method. An iterative solution procedure is devised by explicit determination of the angular flux at the interfaces of segments into which the spatial domain is subdivided. This is accomplished by solving the transport equation in each segment using the incoming flux from adjoining segments as boundary conditions (natural or essential). The interface flux is subsequently updated in a Gauss-Seidel fashion. In each segment, either a phase-space finite element or a finte element-spherical harmonic approximation is used to construct a system of algebraic equations. In two-dimensional X-Y geometry, spatial finite element trial functions of low order are specified on a rectangular or a triangular mesh. In the angular domain, discontinuous trial functions are employed. The local sets of equations are solved directly. On the initial iteration, the segment coefficient matrices are factored and stored for use on subsequent iterations.
- Research Organization:
- Michigan Univ., Ann Arbor (USA)
- OSTI ID:
- 5949809
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BOUNDARY CONDITIONS
FINITE ELEMENT METHOD
ITERATIVE METHODS
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
TRANSPORT THEORY