Thermal-mechanical analyses of the ITER shielding blanket designs
- ITER Garching Join Work Site, Garching bei Munchen (Germany); and others
Thermal-mechanical analyses were performed for the ITER shielding blanket designs to determine its performance parameters under different loading conditions. The shielding blanket designs have austenitic steel structural material, water coolant, and copper first wall coated with beryllium. The choice of copper for the first wall is dictated by the surface heat flux values anticipated during ITER operation. Both austenitic steel and water materials are also performing the shielding function for the vacuum vessel and the toroidal field coils. The water coolant is used at low pressure and low temperature. The shielding blanket consists of sectors that can be installed and removed through the vertical ports between the toroidal field coils except for the sections under the horizontal ports used for blanket testing and plasma heating. The sectors are electrically connected in the toroidal direction to minimize the electromagnetic loads during plasma disruption events. Each sector is divided into several modules. The modules are joined to form a continuous toroidal structure and connected to a continuous back plate. The steel content is about 60-80% of the total volume of the different modules. This composition is around the optimum point for protecting the toroidal field coils from the fusion neutrons. Also, the water fraction is adequate to remove the nuclear heating and the surface heat flux.
- OSTI ID:
- 197006
- Report Number(s):
- CONF-940664--
- Country of Publication:
- United States
- Language:
- English
Similar Records
US Demo test blankets in ITER
Nuclear modules of ITER tokamak systems code