Published 1983
| Version v1
Book
Formulation of a two-fluid model for mixing in LWR bundles
Creators
- 1. Dept. of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA
Description
The space and time averaged two-fluid flow equations are shown to lead to distributive and turbulence terms, which can be lumped into one term to explain two-phase lateral mixing in rod bundles. A model is developed for this mixing and applied into the THERMIT two-fluid code. The model predictions were tested against small rod bundle tests for pressure and quality conditions representative of BWR and PWR conditions. The model successfully predicts the observed low quality in the corner subchannel for BWR conditions. It also predicts the essentially uniform quality distribution for PWR conditions
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-110-X
- Imprint Title
- Thermal hydraulics of nuclear reactors
- Journal Page Range
- p. 433-439.
Conference
- Title
- 2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
- Dates
- 11-13 Jan 1983.
- Place
- Santa Barbara, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17089428
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; BWR TYPE REACTORS; EQUATIONS; FLOW MODELS; FUEL ELEMENT CLUSTERS; MIXING; PRESSURE DEPENDENCE; PWR TYPE REACTORS; QUALITY CONTROL; SPACE DEPENDENCE; T CODES; TIME DEPENDENCE; TURBULENT FLOW; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; CONTROL; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; MATHEMATICAL MODELS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS