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Improvements of COBRA-TF on the effect of flow blockage during a LB LOCA with consideration of fuel relocation phenomenon
- Source :
- Nuclear Engineering and Design. 325:218-231
- Publication Year :
- 2017
- Publisher :
- Elsevier BV, 2017.
-
Abstract
- Coolability of the partially blocked core in a large break loss-of-coolant accident (LB LOCA) is one of the most important thermal-hydraulic concerns for nuclear reactor safety analysis. During blowdown phase and early stage of reflooding phase in the LB LOCA, the prevailing wall-to-vapor convective heat transfer plays an important role on the decay heat removal process. Experiments on single-phase convective heat transfer to vapor were conducted in 5 × 5 heater rod bundles containing 3 × 3 ballooned rods of 90% flow blockage ratio with consideration of fuel relocation phenomenon. The obtained experimental data were used to assess the single-phase heat transfer enhancement models of the COBRA-TF code. The assessment results showed underprediction of local heat transfer downstream of the flow blockage. Therefore, a new correlation has been proposed to improve the prediction capability of the conventional models by more accurately describing the flow blockage effect. The new correlation predicted the local heat transfer satisfactorily within a 20% discrepancy of the experimental data for various kinds of flow blockage configurations.
- Subjects :
- Nuclear and High Energy Physics
Materials science
Convective heat transfer
business.industry
020209 energy
Mechanical Engineering
Heat transfer enhancement
Flow (psychology)
02 engineering and technology
Structural engineering
Mechanics
Nuclear reactor
law.invention
Flow separation
Nuclear Energy and Engineering
law
Heat transfer
0202 electrical engineering, electronic engineering, information engineering
General Materials Science
Decay heat
Safety, Risk, Reliability and Quality
business
Waste Management and Disposal
Boiler blowdown
Subjects
Details
- ISSN :
- 00295493
- Volume :
- 325
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design
- Accession number :
- edsair.doi...........93e971bfe1c7ea9d9e581b26114ae88b