TY - JOUR
T1 - Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature
T2 - Proceedings of the 8th Inert Matrix Fuel Workshop
AU - Arima, T.
AU - Tateyama, T.
AU - Idemitsu, K.
AU - Inagaki, Y.
N1 - Funding Information:
This work was financially supported by the Japan Nuclear Cycle Development Institute. The authors gratefully acknowledge the continuous support by M. Kutsuwada, Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University. The authors also wish to thank K. Wakasugi, Department of Materials Science and Engineering, for his help in EPMA measurements and Dr M. Watanabe, the Center of the Advanced Instrumental Analysis, for her help in XRD measurements.
PY - 2003/6/1
Y1 - 2003/6/1
N2 - Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.
AB - Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.
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U2 - 10.1016/S0022-3115(03)00129-6
DO - 10.1016/S0022-3115(03)00129-6
M3 - Conference article
AN - SCOPUS:0038696371
SN - 0022-3115
VL - 319
SP - 24
EP - 30
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y2 - 16 October 2002 through 18 October 2002
ER -