2022 Fall Meeting

Presentation information

Oral presentation

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

[2D06-08] Fuel Behavior in Accident, Nitride Fuel

Thu. Sep 8, 2022 4:05 PM - 4:55 PM Room D (E1 Bildg.2F No.23)

Chair:Fumihiro Nakamori(CRIEPI)

4:35 PM - 4:50 PM

[2D08] Steam oxidation tests of uranium nitride fuels with additives

*Kyosuke Shibasaki1, Shigeru Kurematsu1, Nozomu Murakami2 (1. MHI Nuclear Development Corporation, 2. MHI)

Keywords:Uranium nitride, Nuclear fuel, Hydrothermal oxidation, Additive

Recently uranium nitride has been researched as one of the candidates for the fuels of small module reactor since it has good properties for nuclear fuels attributed to its high uranium density and high thermal conductivity. However, its high reactivity with steam and water is known as a drawback when using for light water reactor. In this research nitride uranium samples with some additives to mitigate hydrothermal oxidation were fabricated and applied to steam oxidation tests. As a result, we confirmed the tendency that the sample with carbon additive showed high resistance to steam oxidation than non-additive one.