2024 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 505-3 Decommissioning Technology of Nuclear Facilities

[2A05-09] Radioactivity Inventory

Wed. Mar 27, 2024 10:35 AM - 12:00 PM Room A (21Bildg.2F 21-203)

Chair:Koji Dozaki(Tohoku Univ.)

11:35 AM - 11:50 AM

[2A09] Assessment of contamination distribution of “Monju”

(3) Assessment of activation of Ex-Vessel Strage Tank (EVST)

*Yasufumi Kishimoto1, Takuma Kinoshita1, Shotaro Hanaki2, Hirokazu Hayashi2 (1. NESI, 2. JAEA)

Keywords:Fast Reactor, Monju, Decomissioning, Characterization, Fuel handling, Activation

Dismantling in the radiation-controlled area is planned in phase 3 of the “Monju” decommissioning program, but an assessment of contamination of the facilities is essential before starting the dismantling.The unique Ex-Vessel Storage Tank (EVST) unique to "Monju" stores fuel in liquid sodium at 200℃. It requires an evaluation of radioactivity due to neutron-induced structural material activation. The neutron flux distribution and radioactivity of the EVST were assessed by calculation using a 2D RZ system, validating the results through comparison with a 3D system. The assessment confirms that the maximum concentration of activity of activation product in the EVST structural material is at L3 level and generally below clearance level in most areas.