Analysis of sweeping heat loads on divertor plate materials

Conference · Tue Jan 01 04:00:00 EST 1991 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/S0022-3115(09)80095-0· OSTI ID:5987936

Hassanein, A

The heat flux on the divertor plate of a fusion reactor is probably one of the most limiting constraints on its lifetime. The current heat flux profile on the outer divertor plate of a device like ITER is highly peaked with narrow profile. The peak heat flux can be as high as 30--40 MW/m{sup 2} with full width at half maximum (FWHM) is in the order of a few centimeters. Sweeping the separatrix along the divertor plate is one of the options proposed to reduce the thermomechanical effects of this highly peaked narrow profile distribution. The effectiveness of the sweeping process is investigated parametrically for various design values. The optimum sweeping parameters of a particular heat load will depend on the design of the divertor plate as well as on the profile of such a heat load. In general, moving a highly peaked heat load results in substantial reduction of the thermomechanical effects on the divertor plate. 3 refs., 8 figs.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5987936
• Report Number(s): ANL/CP-72824; CONF-911111--12; ON: DE92004145
• Conference Information: Journal Name: Journal of Nuclear Materials Journal Volume: 191-194
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
DIVERTORS
HEAT FLUX
MECHANICAL PROPERTIES
TEMPERATURE DISTRIBUTION
THERMAL ANALYSIS