Coarse mesh finite element method for boiling water reactor physics analysis
Description
A coarse mesh method is formulated for the solution of Boiling Water Reactor physics problems using two group diffusion theory. No fuel assembly cross-section homogenization is required; water gaps, control blades and fuel pins of varying enrichments are treated explicitly. The method combines constrained finite element discretization with infinite lattice super cell trial functions to obtain coarse mesh solutions for which the only approximations are along the boundaries between fuel assemblies. The method is applied to bench mark Boiling Water Reactor problems to obtain both the eigenvalue and detailed flux distributions. The solutions to these problems indicate the method is useful in predicting detailed power distributions and eigenvalues for Boiling Water Reactor physics problems
Availability note (English)
University Microfilms Order No. 84-00,666.Additional details
Publishing Information
- Imprint Pagination
- 99 p.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17044895
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CROSS SECTIONS; EIGENVALUES; FINITE ELEMENT METHOD; FUEL ASSEMBLIES; GROUP THEORY; MESH GENERATION; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NUMERICAL SOLUTION; POWER DENSITY; REACTOR KINETICS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; KINETICS; MATHEMATICS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS