TY - JOUR
T1 - Behavior of fission products zirconium and barium in fastreactor fuel irradiated to high burnup
AU - Sato, Isamu
AU - Furuya, Hirotaka
AU - Arima, Tatsumi
AU - Idemitsu, Kazuya
AU - Yamamoto, Kazuya
N1 - Copyright:
Copyright 2017 Elsevier B.V., All rights reserved.
PY - 1999/9
Y1 - 1999/9
N2 - Barium and Zr generated in nuclear fuels can precipitate as multi-component oxide with some other fission products. In addition, the solubility of Ba in the fuel depends on the oxygenpotential and the temperature and Zr can easily dissolve into the fuel matrix. Therefore, the behavior of the Ba-Zr oxide inclusions during irradiation is rather complex. In this work, the composition of multi-component oxides and the distributions of Ba and Zr as a function of relative radius were evaluated with X-ray microanalysis. As results, the oxide inclusions containing bothBa and Zr and containing only Ba were observed in the fuel irradiated to the burnup of 13.3 and 10.6 at%, respectively. These results were discussed in terms of the solubility of Ba and Zr in the fuel and in terms of the rO2–UO2 phase diagram, together with the radial distributions of Ba and Zr in fuel matrix.
AB - Barium and Zr generated in nuclear fuels can precipitate as multi-component oxide with some other fission products. In addition, the solubility of Ba in the fuel depends on the oxygenpotential and the temperature and Zr can easily dissolve into the fuel matrix. Therefore, the behavior of the Ba-Zr oxide inclusions during irradiation is rather complex. In this work, the composition of multi-component oxides and the distributions of Ba and Zr as a function of relative radius were evaluated with X-ray microanalysis. As results, the oxide inclusions containing bothBa and Zr and containing only Ba were observed in the fuel irradiated to the burnup of 13.3 and 10.6 at%, respectively. These results were discussed in terms of the solubility of Ba and Zr in the fuel and in terms of the rO2–UO2 phase diagram, together with the radial distributions of Ba and Zr in fuel matrix.
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U2 - 10.1080/18811248.1999.9726267
DO - 10.1080/18811248.1999.9726267
M3 - Article
AN - SCOPUS:0033310127
SN - 0022-3131
VL - 36
SP - 775
EP - 780
JO - journal of nuclear science and technology
JF - journal of nuclear science and technology
IS - 9
ER -