Analysis of post boiling transition heat transfer
Description
From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to analyze the mechanism of Post Boiling Transition Heat Transfer and estimate correctly the fuel rod wall temperature. So, in this research, I modeled the phenomena of Post Boiling Transition Heat Transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, I evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data measured by Bennett et. al. which using circular tube and simulating the boiling transition in BWR under the BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately and conservatively. (author)
Additional details
Publishing Information
- Imprint Title
- The 17th national symposium on power and energy systems (SPES 2012)
- Imprint Pagination
- 464 p.
- Journal Page Range
- p. 259-262
Conference
- Title
- 17. national symposium on power and energy systems
- Acronym
- SPES 2012
- Dates
- 21-22 Jun 2012
- Place
- Fukuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 45027383
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; DROPLETS; DRYOUT; FUEL RODS; HEAT TRANSFER; IMPINGEMENT; LIQUIDS; TEMPERATURE DISTRIBUTION; THERMAL RADIATION; TRANSITION BOILING
- Descriptors DEC
- BOILING; ELECTROMAGNETIC RADIATION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; PARTICLES; PHASE TRANSFORMATIONS; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs., 6 figs.