Predictions for heat transfer characteristics in a natural draft reactor cooling system using a second moment closure turbulence model
Creators
- 1. Kawasaki Heavy Industries, LTD., Thermal Technology, Dept., Kawasaki, Kanagawa (Japan)
- 2. Kawasaki Heavy Industries, LTD., R and D Dept., Plant and Infrastructure Engineering Company, Tokyo (Japan)
Description
A numerical study is performed on the natural draft reactor cavity cooling system (RCCS). In the cooling system, buoyancy driven heated upward flow could be in the mixed convection regime that is accompanied by heat transfer impairment. Also, the heating wall condition is asymmetric with regard to the channel cross section. These flow regime and thermal boundary conditions may invalidate the use of design correlation. To precisely simulate the flow and thermal fields within the RCCS, the second moment closure turbulence model is applied. Two types of the RCCS channel geometry are selected to make a comparison: an annular duct with fins on the outer surface of the inner circular wall, and a multi-rectangular duct. The prediction shows that the local heat transfer coefficient on the RCCS with finned annular duct is less than 1/6 of that estimated with Dittus-Boelter correlation. Much portion of the natural draft airflow does not contribute cooling at all because mainstream escapes from the narrow gaps between the fins. This result and thus the finned annulus design are unacceptable from the viewpoint for structural integrity of the RCCS wall boundary. The performance of the multi-rectangular duct design is acceptable that the RCCS maximum temperature is less than 400 degree centigrade even when the flow rate is halved from the designed condition. (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
- 36093919
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR FLOW; CAVITIES; DUCTS; FINS; FORECASTING; GAS COOLED REACTORS; HEAT TRANSFER; NUMERICAL ANALYSIS; REACTOR COOLING SYSTEMS; RECTANGULAR CONFIGURATION; VENTILATION
- Descriptors DEC
- CONFIGURATION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID FLOW; GAS FLOW; MATHEMATICS; REACTOR COMPONENTS; 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 325.pdf; 16 refs., 9 figs., 2 tabs.