One and two dimensional radiation analysis of the Compact Ignition Tokamak

The Compact Ignition Tokamak (CIT) is being proposed as the next major fusion experiment to follow the operations of the Tokamak Fusion Test Reactor (TFTR). CIT is a compact deuterium-tritium-burning tokamak device that is designed to achieve ignition. The high neutron wall loadings, 7-9 MW/m/sup 2/, associated with the operation of this device require that neutronics-related issues be considered in the overall system design. Radiation shielding is required for the protection of both device components and personnel. A close-in igloo shield, 1.8 m nominal thickness, has been designed around the periphery of the tokamak structure to permit personnel access into the test cell after shutdown and to limit the total activation of the test cell components. This paper discusses the major neutronics issues related to the design of the Compact Ignition Experiment, describes the methodologies used to quantify these concerns, and presents the results of radiation transport and activation scoping studies