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Report No.

Irradiation Performance of Uranium-Plutonium Mixed Nitride Fuel Pins in JOYO

not registered ; Iwai, Takashi*; Arai, Yasuo*; Asaka, Takeo

Under the collaboration between JNC and JAERI, two uranium-plutonium mixed nitride fuel pins, whose smear densities were varied by fuel-to-cladding gap sizes, were irradiated in the experimental fast reactor JOYO. Linear heat rate, cladding mid-wall temperature, and burnup in peak were 75 kW/m, 906K, and 4.3 %FIMA, respectively. In order to evaluate nitride fuels for high burnup capability, the effect of fuel swelling behavior on irradiation performance was investigated. The larger smear density induced the greater cladding diameter increments. The wider gap size resulted in the more anisotropic deformations. Threshold temperature of fuel swelling was studied by thermal analysis using radial porosity and xenon retention profiles. To attain higher burnup, experimental results indicate that maximum fuel temperatures should be preferably lower than threshold temperatures of fuel swelling and that the detrimental effects of fuel pellet relocations need to be suppressed and accommodated.



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