Conceptual Radiation Shielding Design of Superconducting Tokamak Fusion Device by PHITS

Abstract

A 3D neutron and photon transport analysis by Monte Carlo transport code system PHITS (Particle and Heavy Ion Transport code System) has been performed for superconducting tokamak fusion device such as JT-60 Super Advanced (JT-60SA). It is possible to make use of PHITS in the port streaming analysis around the devices for the tokamak fusion device, the duct streaming analysis in the building where the device is installed, and the sky shine analysis for the site boundary. The neutron transport analysis by PHITS makes it clear that the shielding performance of the superconducting tokamak fusion device with the cryostat has been improved by the graphical results. From the standpoint of the port and duct streaming, it is necessary to estimate by 3D Monte Carlo code such as PHITS for the neutronics analysis of superconducting tokamak fusion device.

Flexible heat-resistant neutron and gamma-ray shielding resins

“…In a superconducting fusion tokamak device [8], resin will be installed around the port section. The thermal neutron flux level at the port section was estimated by ~ 3.35x10 10 n/cm 2 at 10-year operation.…”

“…Tokamak DD fusion device (DD neutron : 2.45 MeV) such as JT-60SA which will be developed under the Progress in Nuclear Science and Technology, Volume 4, 2014project Europe and Japan is fabricated from many stainless steels [8]. The annual neutron yields of JT-60SA will increase by about fifty times the permitted amount of neutron yields in the existing JT-60 device.…”