Published 2005 | Version v1
Miscellaneous

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.