Published 2009
| Version v1
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Heat transfer in a seven-rod test bundle with supercritical pressure water (1). Experiments
Creators
- 1. Japan Atomic Energy Agency, Fusion Research and Development Directorate, Naka, Ibaraki (Japan)
- 2. Kyushu Univ., Fukuoka (Japan)
- 3. Tokyo Univ., Tokyo (Japan)
Description
Heat transfer experiments in a seven-rod test bundle with supercritical pressure water has been carried out. The pressure drop and heat transfer coefficients (HTCs) in the test section are evaluated. In the present limited conditions, difference between HTCs at the surface facing the sub-channel center and those at the surface in the narrowest region between rods is not observed. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of 2009 international congress on advances in nuclear power plants
- Imprint Pagination
- [2572 p.]
- Journal Page Range
- [1 p.]
- Report number
- INIS-JP--123
Conference
- Title
- 2009 international congress on advances in nuclear power plants
- Acronym
- ICAPP2009
- Dates
- 10-14 May 2009
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43088089
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; ENTHALPY; FAST REACTORS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; HEATERS; PRESSURE DROP; SUPERCRITICAL STATE; TEMPERATURE DISTRIBUTION; TEMPERATURE MEASUREMENT; WATER
- Descriptors DEC
- ENERGY TRANSFER; EPITHERMAL REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9464.pdf; 2 figs.