2020 Fall Meeting

Presentation information

Oral presentation

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

[2E08-13] Nitride fuel

Thu. Sep 17, 2020 2:45 PM - 4:25 PM Room E (Zoom room 5)

Chair:Kunihiro Itoh(NDC)

2:45 PM - 3:00 PM

[2E08] R&D on Nitride Fuel Ctcle for MA Transmutation to Enhance Safety and Economy

(14)Dimensional Recovery of He-accumulated Nitride Pellet Containing Cm by Annealing

*Masahide Takano1, Seiya Takaki1 (1. JAEA)

Keywords:Minor actinide, Transmutation, Nitride fuel, He gas swelling, Defect recovery

We performed annealing experiments on a Cm-bearing nitride fuel pellet, in which Frenkel defects and He atoms accumulated due to alpha decay at room temperature, and obtained data on dimensional change arrising from defect recovery and gaseous He release. By comparing the annealing curve and cross-sectional images with those for the Cm-bearing dioxide, we found that the mechanism of the nitride behavior at high temperatures is different from that of dioxide.