Heat transfer experiments and numerical analysis of supercritical pressure water in seven-rod test bundle
Creators
- 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
- 2. Japan Atomic Energy Agency, Naka Fusion Institute, Naka, Ibaraki (Japan)
Description
The heat transfer experiment of supercritical pressure water in a seven-rod test bundle, which simulates SCWR rod bundle, is performed to investigate heat transfer around the fuel rods. It is confirmed from the experiment that pressure drop in the rod bundle is approximately stable with increase of bulk temperature, and that obvious difference in rod surface temperatures between the surface facing to narrowest region between rods and that facing to the center of subchannel can hardly be seen. ACE-3D is applied to the experimental analysis of seven-rod bundle heat transfer experiments. It is confirmed that ACE-3D can predict the rod surface temperature within variation in experimental results by including thermal conduction in the simulated fuel rod, that improvement in prediction accuracy of the rod surface temperature in high bulk enthalpy region remains to be solved, that ACE-3D can also predict the pressure drop by taking into account the pressure drop of grid spacers with an experimental correlation, and that difference of flow field in subchannels adjacent to between the center rod and the shroud wall increases when the bulk enthalpy is close to the pseudo critical enthalpy. (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [14 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43093574
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; ENTHALPY; FUEL ELEMENT CLUSTERS; FUEL RODS; NUMERICAL ANALYSIS; PRESSURE DROP; SPACERS; SUPERCRITICAL STATE; THERMAL CONDUCTION; WATER; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT TRANSFER; HYDROGEN COMPOUNDS; MATHEMATICS; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1437.pdf; 10 refs., 16 figs., 3 tabs.