Effects of the spatial discretization and temperature distribution approximation on BWR assembly calculations
- 1. Chuden CTI Co., Ltd., Naka-ku, Nagoya (Japan)
- 2. Chubu Electric Power Co., Inc., Midori-ku, Nagoya (Japan)
- 3. Nagoya Univ., Dept. of Material Science and Energy Engineering (Japan)
Description
The effects of the spatial discretization and temperature distribution approximation on the BWR assembly calculation were studied using the continuously energy Monte Carlo burn-up calculation under several conditions. The radial-division, temperature-distribution, and azimuthal-division effects of fuel pellet for BWR fuel (8*8, wide-water-rod) were investigated. The calculation results indicate that the effect of the temperature distribution approximation on the assembly calculation is negligible, even if a pin-averaged temperature was assigned to all fuel pins. The effect of the spatial discretization of fuel pellet in the azimuthal direction brings about a 0.15% dk/k prediction error in k-infinity. This effect is caused by the change of the burnup characteristics of the Gd burn-up in the Gd-rods. Therefore, the azimuthal-division of Gd-rods is desirable to reduce the spatial discretization effect for BWR assembly with higher Gd fuel rods. (authors)
Availability note (English)
Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)Additional details
Publishing Information
- Publisher
- SFEN
- Imprint Place
- Paris (France)
- Imprint Pagination
- 13 p.
- Report number
- INIS-FR--09-0333
Conference
- Title
- M-C 2005- International topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications
- Dates
- 12-15 Sep 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 40054846
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; FUEL ASSEMBLIES; M CODES; MESH GENERATION; REACTIVITY; TEMPERATURE DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.