10:35 AM - 10:50 AM
[1G03] Study on heat removal design for shielding wall of irradiation test cell in Fusion Neutron Source
Keywords:A-FNS, Fusion Neutron Source, Shielding Wall , Liquid Lithium Target, MCNP, Nuclear Heating
In the fusion neutron source, there is a plan to irradiate fusion reactor materials using high-energy neutrons generated from a liquid Li target. The generated neutron energy is up to 55 MeV, and nuclear heating of up to 0.1 W/cm3 is generated in the shielding wall of the irradiation test cell. The temperature of the shielding wall rises due to nuclear heating, and there is concern about the deterioration of the shielding wall such as concrete. In this study, the nuclear heating for each shielding wall material was calculated using the Monte Carlo particle transport calculation code MCNP. Based on the obtained nuclear heating values, a thermal analysis of the shielding wall was performed.
Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.