Published 1983
| Version v1
Book
COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR
- 1. Argonne National Lab., 9700 South Cass Ave., Argonne, IL
Description
Fluid and thermal mixing in a model cold leg and downcomer of a PWR was analyzed using COMMIX-1A. The present analysis differs from previous analyses in three major aspects. First, extremely fine meshes were used to minimize numerical diffusion in the analysis. Second, one-equation (k) turbulence model was used to better model the turbulent flow. Third, curved surfaces were modeled by several slanted planes to better represent the geometries. By using these improvements, CREARE 1/5-scale test No. 51 was reanalyzed. Significant improvements were achieved in the comparisons between the COMMIX calculations and the experimental data
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-919784-02-X
- Imprint Title
- Proceedings of the international conference on numerical methods in nuclear engineering. Volume 1
- Journal Page Range
- p. 555-579.
Conference
- Title
- International conference on numerical methods in nuclear engineering.
- Dates
- 6-9 Sep 1983.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17051784
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; DIFFUSION; FLOW MODELS; HEAT TRANSFER; PIPES; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; TURBULENT FLOW
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS