2021 Annual Meeting

Presentation information

Oral presentation

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

[3K01-06] Fast Reactor Recycling

Fri. Mar 19, 2021 10:15 AM - 12:00 PM Room K (Zoom room 11)

Chair: Ken Kurosaki (Kyoto Univ.)

11:15 AM - 11:30 AM

[3K05] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(5)Development of measurement technique for local melting point of fuel pellet with laser heating

*Tatsumi Arima1, Masato Kato2 (1. Kyushu Univ., 2. JAEA)

Keywords:Melting point, FBR, MOX fuel, Actinides

In MOX fuels irradiated in FBR, each constituent element of fuel has a different concentration profile in the radial direction. Though the melting point is one of the most important properties for a nuclear fuel management, it has been measured for one pellet so far. In this project, we focus on the development of measurement technique for local melting point of fuel pellet where each actinide has a different concentration profile.