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Journal Articles

Short-term irradiation behavior of low-density americium-doped uranium-plutonium mixed oxide fuels irradiated in a fast reactor

Maeda, Koji; Katsuyama, Kozo; Ikusawa, Yoshihisa; Maeda, Seiichiro

Journal of Nuclear Materials, 416(1-2), p.158 - 165, 2011/09

 Times Cited Count:16 Percentile:75.64(Materials Science, Multidisciplinary)

In order to evaluate the thermal behavior of low-density uranium and plutonium mixed oxide fuels containing several percent of americium (Am-MOX), fuel irradiation test (B14) was conducted using the experimental fast reactor. Pellet-cladding gap width and O/M ratio of oxide fuels were specified as experimental parameters. Four fuel pins were irradiated step-by-step in consideration of fuel restructuring during 48 hours as pre-conditioning before full power reactor operation. The irradiation history, i.e. linear power, was simulated the conventional FBR oxide fuel pins. And the linear power was rapidly increased up to 47 kW/cm for 10 minutes to simulate the transient condition. After the irradiation, ceramography samples were taken from the axial position of each fuel pins where the fuel centerline temperature reached the maximum during irradiation. The result was investigated relative to those of other irradiated fuels.

Journal Articles

Fission gases and helium gas behavior in irradiated mixed oxide fuel pin

Sato, Isamu; Katsuyama, Kozo; Arai, Yasuo

Journal of Nuclear Materials, 416(1-2), p.151 - 157, 2011/09

 Times Cited Count:11 Percentile:63.92(Materials Science, Multidisciplinary)

Release behavior of fission gases such as Kr and Xe from fuel pellets has been extensively investigated from the viewpoints of increase of internal pressure of fuel pins and swelling of fuel pellets. He also contributes to increase the internal pressure of fuel pins, especially in the case of minor actinide containing MOX fuel. In this work, the amounts of fission gases and He in a fuel pin irradiated in the experimental fast reactor, JOYO, to -50 GWd/t as a pin average burnup were quantitatively measured by pin puncture and pellet heating tests. As results, the release fractions of fission gases from fuel pellets were about 50%, but He was released by more than 70%. In addition, 20% of He may be derived from $$alpha$$-decay of actinide species after irradiation. It was suggested that most of He generated during irradiation was released because of the high temperature like in fast reactor environment.

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