Engineering and thermal-hydraulics design of PFC cooling for SST-1 Tokamak
Creators
- 1. KAERI, Taejon (Korea, Republic of)
Description
The main consideration in the design of the PFC cooling for SST-1 tokamak is the steady state heat removal of upto 1MW/m2. The PFC also has been design to withstand the peak heat fluxes without significant erosion such that frequent replacement is not necessary. Proper brazing of cooling tube on the copper back plate is necessary for the efficient heat transfer from the tube to the back plate. Design considerations included 2-D steady state and transient tile temperature distribution and resulting thermal loads in PFC during baking, and cooling, coolant parameters necessary to maintain optimum thermal-hydraulic design, and tile fitting mechanism. Finite Element (FE) models using ANSYS have been developed to conduct the heat transfer and stress analyses of the PFC to understand its thermal and mechanical behaviors. The temperature distribution results for different PFC obtained by FE results were assessed by comparison with 2-D Finite Difference code. The results of the calculation led to a good understanding of the coolant flow behavior and the temperature distribution in the tube wall and the different parts of the PFC. The contact at the brazed joint of the tube to the backplate is critical for the above application. The manufactured modules need to be evaluated for the quality of brazed joint. Using an infra-red-camera, spatial and temporal evaluation of the temperature profile is studied under various flow parameters. These results of this study will be presented in details in this paper
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the tenth international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [20 p.]
Conference
- Title
- NURETH-10
- Dates
- 5-11 Oct 2003
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36067406
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BAKING; BRAZING; COOLING; CRITICAL HEAT FLUX; DESIGN; HEAT TRANSFER; THERMAL HYDRAULICS; THERMAL STRESSES; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ENERGY TRANSFER; FABRICATION; FLUID MECHANICS; HEAT FLUX; HEATING; HYDRAULICS; JOINING; MECHANICS; STRESSES; THERMONUCLEAR DEVICES; WELDING
Optional Information
- Notes
- 16 refs, 17 figs, 3 tabs