TY - JOUR
T1 - Observation of the spatial distribution of hydrogen in Zircaloy-2 oxidized in H2O steam at 723 K by a technique of tritium microautoradiography
AU - Isobe, K.
AU - Hatano, Y.
AU - Sugisaki, M.
N1 - Funding Information:
The authors would like to express their sincere thanks to Mr K. Shimose of Faculty of Engineering, Kyushu University for helpful assistance in the experiments. The present study was partly supported by a Grant-in-Aid for Scientific Research (B) of the Ministry of Education, Science, Sports and Culture, No. 02452295.
PY - 1997/9/1
Y1 - 1997/9/1
N2 - The spatial distribution of hydrogen in Zircaloy-2, which was oxidized in H2O steam at 723 K and quenched down to room temperature, was examined by a technique of tritium autoradiography. Tritium was introduced into the specimen through the oxide layer by the cathodic charging method using tritium water at room temperature. The radiograph of the cross-section was observed by a scanning electron microscope. Hydrogen was densely distributed on the grain boundary and in the grain of the inner base alloy, but it was scarcely distributed in the oxide layer. Hydrogen was locally distributed, however, in the region corresponding to the intermetallic precipitates embedded in the oxide layer. The mechanism of penetration of tritium through the oxide layer during the cathodic charging was discussed.
AB - The spatial distribution of hydrogen in Zircaloy-2, which was oxidized in H2O steam at 723 K and quenched down to room temperature, was examined by a technique of tritium autoradiography. Tritium was introduced into the specimen through the oxide layer by the cathodic charging method using tritium water at room temperature. The radiograph of the cross-section was observed by a scanning electron microscope. Hydrogen was densely distributed on the grain boundary and in the grain of the inner base alloy, but it was scarcely distributed in the oxide layer. Hydrogen was locally distributed, however, in the region corresponding to the intermetallic precipitates embedded in the oxide layer. The mechanism of penetration of tritium through the oxide layer during the cathodic charging was discussed.
UR - http://www.scopus.com/inward/record.url?scp=0031234197&partnerID=8YFLogxK
U2 - 10.1016/S0022-3115(97)00129-3
DO - 10.1016/S0022-3115(97)00129-3
M3 - 学術論文
AN - SCOPUS:0031234197
SN - 0022-3115
VL - 248
SP - 315
EP - 318
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -