Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
- 1. Nuclear Power Institute of China, Chengdu (China)
- 2. Paul Scherrer Institute, Villigen PSI (Switzerland)
- 3. University of Applied Sciences and Arts of Southern Switzerland, Lugano-Viganello (Switzerland)
Description
Turbulent mixing in buoyant flows is an essential mechanism involved in many scenarios related to nuclear safety in nuclear power plants. Comprehensive understanding and accurate predictions of turbulent buoyant flows in the reactor are of crucial importance, due to the function of mitigating the potential detrimental consequences during postulated accidents. The present study uses URANS methodology to investigate the buoyancy-influenced flows in the reactor pressure vessel under the main team line break accident scenarios. With a particular focus on the influence of turbulent heat flux closure models, various combinations of two turbulence models and three turbulent heat flux models are utilized for the numerical simulations of three ROCOM tests which have different characteristic features in terms of the flow rate and fluid density difference between loops. The simulation results are compared with experimental measurements of the so-called mixing scalar in the downcomer and at the core inlet. The study shows that the anisotropic turbulent heat flux models are able to improve the accuracy of the predictions under conditions of strong buoyancy whilst in the weak buoyancy case, a major role is played by the selected turbulence models with essentially a negligible influence of the turbulent heat flux closure models
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 54
- Journal Issue
- 11
- Journal Page Range
- p. 4359-4372
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 55095375
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COOLANT LOOPS; EXPERIMENTAL DATA; FLUID FLOW; HEAT FLUX; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; PRESSURE VESSELS; REACTORS; RISK ASSESSMENT; SAFETY; SIMULATION; TURBULENT FLOW; TURBULENT HEATING
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; FLUID FLOW; HEATING; INFORMATION; MATHEMATICS; NUCLEAR FACILITIES; NUMERICAL DATA; PLASMA HEATING; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 37 refs, 18 figs, 2 tabs