Verification of the three-dimensional FLAME code
Description
FLAME calculations are compared with operating data from Oconee Unit 1 and with two independent three-dimensional PDQ07 calculations for a feed-and-bleed plant containing lumped burnable poison. The Oconee 1 comparisons consider both steady-state and transient data.The steady-state calculations are compared with operating data from two cycles of operation. The comparisons with PDQ07 calculations are for a design transient. Direct comparisons are made between calculations and measurements for the Oconee 1 analyses. No uncertainty is applied to measured power densities. The difference in measured and calculated total peak for 95 percent of the assemblies considered in these comparisons is less than 5.3 percent. Based on these analyses, it is concluded that FLAME can calculate the total peak to within 5.3 percent for both steady-state and transient plant conditions. The maximum deviation in the total peak calculated by FLAME and one of the PDQ07 calculations is 5.6 percent. The maximum deviation with the other PDQ07 calculation is 2.5 percent. It is concluded that the FLAME calculations gave the most conservative results of the three
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR power distributions
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- BAW--10125
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7275820
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; F CODES; OCONEE-1 REACTOR; POWER DENSITY; PWR TYPE REACTORS; REACTOR KINETICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Babcock and Wilcox, Lynchburgh, VA.