ITER: Nuclear engineering aspects

A summary of the design guidelines and the selection rationale of the initial options for the in-vessel components of ITER is presented. A low temperature/pressure water coolant and solution annealed 316 austenitic steel are recommended to provide high reliability of first wall/blanket structure. Carbon based materials are chosen as armour both on first wall and divertor during the physics phase of operation, and high Z materials are considered as a possibility for the technology phase. Three blanket options are proposed as initial ones, with solid breeder, LiPb eutectic and Li salt aqueous solution. The tritium breeding capability and the requirements for recovery have been identified. The selection of the inboard shield/blanket composition provides magnet radiation protection and permits extended plasma operation in the physics phase. Also presented are fuel cycle design alternatives for fuelling exhaust, tritium recovery and processing. Testing requirements and schedule are considered. (author). 3 figs, 2 tabs