Assessment of Capabilities for Ensuring Radiation Safety of Personnel at the T-15MD Facility during Operation with Deuterium Fuel

Abstract

Currently, the T-15MD tokamak is successfully conducting research on hydrogen plasma in accordance with the recently published Program [1]. One of the possible ways to further develop the T-15MD tokamak is to conduct experimental campaigns using deuterium fuel. Deuterium pulses will be accompanied by the release of D–D fusion reaction neutrons, which, as a result of radiation capture by the structural materials, will lead to the formation of a source of prompt gamma quanta, and the activation and transmutation of materials will lead to the release of secondary gamma radiation. The appearance of these radiation sources necessitates the selection of technical means and organizational measures to ensure the radiation safety conditions. The paper presents the calculated configurations of the radiation shield that is considered optimal and ensures the practical feasibility and safety of personnel working at the T-15MD tokamak using deuterium fuel.