2023 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2C10-15] Low Decontaminated Minor Actinide Bearing Mixed Oxide Fuels, Fast Reactor Recycle

Thu. Sep 7, 2023 2:45 PM - 4:20 PM Room C (IB Bildg.1F IB015)

Chair:Tsuyoshi Yaita(JAEA)

3:15 PM - 3:30 PM

[2C12] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(12)Estimation of radial thermal conductivity of multilayer pellets prepared by 3D printer using 2 kinds of transient plane heat source method

*Kaito Kimura1, Masayoshi Uno1, Takashi Onitsuka1 (1. Univ. of Fukui)

Keywords:Thermal conductivity, Transient plane heat source method, Hot Disk method, Multilayer pellets, Irradiated pellets

In the irradiated fast reactor pellets the precipitates form concentrically. The objective of this research is to confirm whether thermal conductivity of this multilayer pellets prepared by 3D printer can be measured using transient plane heat source methods and to find the difference thermal conductivity between the axial direction and the radial direction of the sample. For that Hot Disk method was used to measure the isotropic thermal conductivity, and the TCi method was used to measure the axial thermal conductivity. Then, thermal conductivity in the radial direction was evaluated from them.

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