CHF prediction by a FIDAS code based on the three-fluid, three-field and film dryout model
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., O-arai-machi, Ibaraki-ken (Japan)
Description
The Film Dryout Analysis Code in Subchannels, FIDAS, has been developed with a main objective of predicting the dryout and post-dryout heat transfer in a channel and rod bundles. FIDAS code can predict the dryout without any empirical CHF correlations by introducing an annular flow modeling and 'the film dryout criterion' in which dryout is indicated when there is no liquid film on the heated surface. Furthermore, droplet entrainment and deposition models are newly developed to improve the prediction accuracy on dryout founded on entrainment by interfacial shear force balance at the roll wave crest, deposition by turbulent diffusion mechanism in vapor core and deposition suppression phenomenon by vaporization on the heater surface. Dryout experiment for round tubes which were carried out in RISO, AERE and AEEW are analyzed to demonstrate the performance of FIDAS code. Predictions by FIDAS code agree well with the experiments in the critical heat flux
Additional details
Publishing Information
- Publisher
- Clean Energy Research Inst. University of Miami.
- Imprint Place
- Coral Gables, FL (USA)
- Imprint Title
- The 5th Miami international symposium on multi-phase transport and particulate phenomena (Condensed Papers)
- Imprint Pagination
- 181 p.
- Journal Page Range
- p. 43.
Conference
- Title
- 5. Miami international symposium on multi-phase transport and particulate phenomena.
- Dates
- 12-14 Dec 1988.
- Place
- Miami Beach, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21006527
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; DRYOUT; F CODES; FLOW MODELS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; HEAT FLUX; MATHEMATICAL MODELS; REACTOR CHANNELS; REACTOR COMPONENTS; SAFETY; SIMULATION
Optional Information
- Secondary number(s)
- CONF-881202--.