Neutron-physical analysis of the neutral particle analyser system intended for International Thermonuclear Experimental Reactor plasma diagnostics

Abstract

The paper presents the results of the neutron-physical analysis of the International Thermonuclear Experimental Reactor equatorial port 11 with the diagnostic systems of neutral particle analysers located at this port. As a result of the calculations, the neutron and gamma fluxes on the analyser components (diamond-like foils, detectors and analyser magnets) were obtained. The energy deposition on these elements was also estimated. The calculations were made for the area covering the port region from the shielding plug end to the cryostat, as well as for the space behind the biological shield in the room, where the analyser system is mounted. The thickness and height of the shielding installed in front of the system, which provides an acceptable dose for access of personnel both during reactor operation and after its shutdown, were estimated. The recommendations to continue the calculations are given.