2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-6 Fusion Reactor System, Design, Application

[3G01-05] Design of Liquid Metal Blanket

Thu. Mar 28, 2024 9:30 AM - 10:55 AM Room G (21Bildg.3F 21-317)

Chair:Shunsuke Kenjo(QST)

10:00 AM - 10:15 AM

[3G03] Research and development of liquid breeder blanket of commercial laser inertial fusion reactor

(3) Tritium breeding scenario of laser inertial fusion reactor with deuterium fuel

*Kaoru Omiya1, Yoshitaka Mori2,3, Kazuki Matsuo2, Masatoshi Kondo1 (1. Tokyo Tech, 2. EX-Fusion, 3. GPI)

Keywords:Laser fusion reactor, Tritium breeding, System dynamics

The purpose is to clarify the operation scenario of commercial laser inertial fusion reactor with deuterium (D) fuel, which can produce tritium (T) necessary for steady-state D-T operation. The standard mean residence time of tritium to pass through each component of the fuel cycle is estimated. The change of tritium inventory in the reactor components was investigated by means of system dynamics simulation. The operation days required to reach steady-state D-T operation are 23 days based on the specification of KOYO-Fast. The excess T production rate is 11 g/MWth/yr and approximately 164 times higher than that by heavy water reactor. The cost of external electricity required for the D-D operation corresponds to 0.03 % of capital cost of commercial reactor.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password