Design, fabrication and testing of helium cooled module
- General Atomics, San Diego, CA (United States)
The International Thermonuclear Reactor (ITER) will have a single null divertor with total power flow of 240 MW and a peak heat flux of about 5 MW/m{sup 2}. The reference coolant for the divertor is water. However, helium offers many advantages from safety considerations, and is a viable alternative to water cooling. In order to prove the feasibility of helium cooling at ITER relevant heat flux conditions, a task was undertaken to design fabricate and test a helium cooled module. The testing was to be carried out at Sandia National Laboratory, Albuquerque (SNLA). The specifications of the loop and the electron beam testing facility (4 MPa pressure, 32 g/s of flow, 30 kW beam power) determined the maximum size of the module that could tested. The divertor module was designed for twice the ITER heat flux, was made from dispersion strengthened copper, with a heat flux surface of 25 mm wide and 80 mm long.
- OSTI ID:
- 197073
- Report Number(s):
- CONF-940664--
- Country of Publication:
- United States
- Language:
- English
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