Root-cause analysis of the better performance of the coarse-mesh finite-difference method for CANDU-type reactors
Creators
- 1. Candu Energy Inc., 2285 Speakman Dr., Mississauga, ON L5B 1K (Canada)
Description
Recent assessment results indicate that the coarse-mesh finite-difference method (FDM) gives consistently smaller percent differences in channel powers than the fine-mesh FDM when compared to the reference MCNP solution for CANDU-type reactors. However, there is an impression that the fine-mesh FDM should always give more accurate results than the coarse-mesh FDM in theory. To answer the question if the better performance of the coarse-mesh FDM for CANDU-type reactors was just a coincidence (cancellation of errors) or caused by the use of heavy water or the use of lattice-homogenized cross sections for the cluster fuel geometry in the diffusion calculation, three benchmark problems were set up with three different fuel lattices: CANDU, HWR and PWR. These benchmark problems were then used to analyze the root cause of the better performance of the coarse-mesh FDM for CANDU-type reactors. The analyses confirm that the better performance of the coarse-mesh FDM for CANDU-type reactors is mainly caused by the use of lattice-homogenized cross sections for the sub-meshes of the cluster fuel geometry in the diffusion calculation. Based on the analyses, it is recommended to use 2 x 2 coarse-mesh FDM to analyze CANDU-type reactors when lattice-homogenized cross sections are used in the core analysis. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-085-9
- Imprint Pagination
- 16 p.
Conference
- Title
- Conference on Advances in Reactor Physics - Linking Research, Industry, and Education
- Acronym
- PHYSOR 2012
- Dates
- 15-20 Apr 2012
- Place
- Knoxville, TN (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 44063407
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CROSS SECTIONS; FINITE DIFFERENCE METHOD; GEOMETRY; HEAVY WATER; NUCLEAR FUELS; PERFORMANCE; PWR TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; DEUTERIUM COMPOUNDS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; ITERATIVE METHODS; MATERIALS; MATHEMATICAL SOLUTIONS; MATHEMATICS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.