Published 2004 | Version v1
Computer medium

Predictions for heat transfer characteristics in a natural draft reactor cooling system using a second moment closure turbulence model

  • 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)

Part of:
NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety

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.