Predicted two-phase flow structure in fuel a bundle of an advanced light-water reactor
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
- 2. Yamato System Engineering Co. Ltd., Hitachi, Ibaraki (Japan)
Description
In order to predict the water-vapor two-phase flow structure in a fuel bundle of an advanced light-water reactor, large-scale numerical simulations were carried out using a newly developed two-phase flow analysis method and a highly parallel-vector supercomputer. Conventional analysis methods such as subchannel codes need composition equations based on the experimental data. In case that there are no experimental data regarding the thermal-hydraulics in the tight-lattice core, therefore, it is difficult to obtain high prediction accuracy on the thermal design of the advanced light-water reactor. Then, a new analysis method using the large-scale direct numerical simulation of water-vapor two-phase flow was proposed. The axial velocity distribution in a fuel bundle changed sharply around a spacer. The bridge formation occurred at the position of adjacent fuel rods where an interval is the narrowest, and vapor mainly flows downstream the triangular part where the interval of adjacent fuel rods is large. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 14 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36093853
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DISTRIBUTION; FLOW MODELS; FUEL ELEMENT CLUSTERS; MODIFICATIONS; NUMERICAL ANALYSIS; SIMULATION; SPACERS; TWO-PHASE FLOW; VAPORS; VELOCITY; WATER; WATER COOLED REACTORS
- Descriptors DEC
- FLUID FLOW; FLUIDS; FUEL ASSEMBLIES; GASES; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; MATHEMATICS; OXYGEN COMPOUNDS; REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name THURSDAY October 7, 2004, Paper ID N6P 022.pdf; 12 refs., 10 figs.