Prediction of the turbulent mixing in bare rod bundles
Creators
- 1. Cheju National University, Cheju (Korea, Republic of)
- 2. Ministry of Science and Technology, Gwacheon (Korea, Republic of)
Description
The turbulent mixing rate is very important variable in the thermal-hydraulic design of nuclear reactors. In this study, the turbulent mixing rate the fluid flows through rod bundles is estimated with the scale analysis on the flow pulsation phenomenon. Based upon the assumption that the turbulent mixing is composed of molecular motion, isotropic turbulent motion (turbulent motion without the flow pulsation), and flow pulsation, the scale relation for the mixing is derived as a function of P/D, Re, and Pr. The derived scale relation is compared with published experimental results and shows good agreements. Since the scale relation is applicable to various Prandtl number fluid flows, It is expected to be useful for the thermal-hydraulic analysis of liquid metal coolant reactors as well as of moderate Prandtl number coolant reactors. (author). 15 refs. 5 figs
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Nuclear Society
- Journal Volume
- 31
- Journal Issue
- 1
- Journal Page Range
- p. 104-115
- ISSN
- 0372-7327
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 30059369
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BREEDING; COOLANTS; FLUID FLOW; FUEL ELEMENT CLUSTERS; GAS FLOW; HYDRAULICS; LIQUID METALS; PRANDTL NUMBER; PULSATIONS; REACTOR COOLING SYSTEMS; THERMAL CONDUCTION; THERMODYNAMIC PROPERTIES; TRANSMUTATION; TURBULENCE; TURBULENT FLOW
- Descriptors DEC
- COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID FLOW; FLUIDS; FUEL ASSEMBLIES; HEAT TRANSFER; LIQUIDS; METALS; NUCLEAR FUEL CONVERSION; PHYSICAL PROPERTIES; REACTOR COMPONENTS