Title :
Two dimensional LOCA analysis for fusion reactors
Author :
Attaya, H. ; Gohar, Y.
Author_Institution :
Fusion Power Program, Argonne Nat. Lab., IL, USA
Abstract :
The results of a two-dimensional loss-of-coolant accident (LOCA) analysis for the inboard shield of a US design proposed for the International Thermonuclear Experimental Reactor (ITER) are reported. The finite-element heat transfer code TOPAZ2D has been used to model the inboard shield. It is assumed that the plasma continues to operate for 10 s after the onset of the LOCA. During this time, the heat source consists of the heat flux on the first wall (FW) tiles, the nuclear heating, and the radioactive decay heat. After the first 10 s, the decay heat becomes the only heat source. The magnets are assumed to be intact during and after the accident, and heat is radiated from the shield to the magnet´s thermal shield, which is at 70K. The temperature response of the shield has been calculated up to 12.8 after the LOCA starts. The results show that the temperature everywhere in the shield is tolerable. The maximum temperature of the back of the shield, which is made of lead, reaches 41°C at the end of the 10-s plasma-on period. The maximum temperature of the first wall reaches 520°C at 7.5 h after shutdown and then decreases slowly
Keywords :
Tokamak devices; fusion reactor safety; fusion reactor theory and design; nuclear engineering computing; 10 s; 520 degC; 7.5 h; ITER; International Thermonuclear Experimental Reactor; LOCA; TOPAZ2D; first wall; fusion reactors; heat flux; inboard shield; maximum temperature; nuclear heating; radioactive decay heat; two-dimensional loss-of-coolant accident; Accidents; Finite element methods; Fusion reactor design; Fusion reactors; Heat transfer; Heating; Inductors; Plasma sources; Plasma temperature; Tiles;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102408
