Gamma dose evaluation of ITER based on neutron activation calculation using monte carlo method

Abstract

ITER (International Thermonuclear Experimental Reactor) is an international nuclear fusion research and engineering project, which is the largest international science project and most advanced experimental tokamak nuclear fusion reactor. Dose rates assessment and gamma radiation due to the neutron activation of the solid structures in ITER is important from the radiological point of view. Therefore, the gamma dosimetry considered in this case is based on neutron activation due to the Deuterium-Tritium (DT) plasma burning with neutrons production rate at 14.1 MeV. The aim of this study is the assessment of gamma dose rates around ITER by considering neutron activation and delay gammas. To achieve the aim, the ITER system and its components were simulated by Monte Carlo method. Also to increase the accuracy and precision of the absorbed dose assessment the activation of walls around the ITER system were considered in the simulation. The results of this research showed that the total dose rate level near to the outside of bio-shield wall of Tokamak hall is not more than dose limits. © 2012 RAD Conference Proceedings. All rights reserved.