A model considering quality distribution in transverse profile for critical power prediction in different scale tight lattice bundles
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
In this paper, a critical power model is proposed among different size tight lattice bundles. The model takes into account quality distribution in cross-sectional profile. A quality distribution factor is introduced and is written as a function of mass velocity and radial power distribution in divided sub-channels. Boiling Transition (BT) is assumed occurring in the sub-channel that possesses highest quality distribution factor. Around RMWR operating conditions, for bundles that has same axial heated pattern but being different size, BT is assumed occurring when local quality reach local critical quality. Based on the model, critical power in JAERI 37-rod tight lattice bundle is predicted from JAERI 7-rod tight lattice bundle data. The predicted values are compared with experimental data. The model then is applied to predict critical power in 127-rod and 217-rod bundles. At last, scale factors are evaluated. (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
- 12 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
- 36053669
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; DRYOUT; FLOW MODELS; FUEL ELEMENT CLUSTERS; FUEL RODS; GAS FLOW; LIQUID FLOW; POWER DENSITY; POWER DISTRIBUTION; REACTOR LATTICES; TRANSITION BOILING; TWO-PHASE FLOW
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; MATHEMATICAL MODELS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED 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 TUESDAY October 5, 2004, Paper ID N6P 198.pdf