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Ogiyanagi, Jin; Chimi, Yasuhiro; Shimada, Sachio*; Nakamura, Takehiko; Abe, Katsuhiro*
Journal of Nuclear Science and Technology, 47(2), p.197 - 201, 2010/02
Times Cited Count：1 Percentile：9.99(Nuclear Science & Technology)The terminal solid solubility (TSS) of hydrogen during hydride dissolution/precipitation is determined by the differential scanning calorimetry technique for non-irradiated hafnium (Hf) that is used as control rods of light water reactors. The hydrogen concentration in hydrogenated Hf samples ranged from 27 to 300 wt ppm. The reliability of the TSS data obtained for Hf was confirmed by those for Zircaloy-2 (Zry-2) obtained in this study with the literature data, and best-fit equations for the obtained TSS curves for Hf are derived. The TSS for Hf at 573 K, which corresponds to an operational temperature of control rods in boiling water reactors, is in the range of 10-15 wt ppm, and is found to be 1/5-1/7 of the TSS for Zry-2.
Shimada, Sachio; Chuto, Toshinori; Nagase, Fumihisa; Fuketa, Toyoshi
no journal, ,
no abstracts in English
Chimi, Yasuhiro; Ogiyanagi, Jin; Shimada, Sachio*; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*
no journal, ,
In order to understand basic irradiation behavior of hafnium (Hf) which is used as the control rod for the Boiling Water Reactor (BWR), we are planning irradiation tests of Hf at Japan Materials Testing Reactor (JMTR). Prior to the irradiation tests, some of the fundamental properties of unirradiated Hf were obtained. In the present report, we discuss the results of optical microscope and SEM observations, and crystal orientation measurement.
Shimada, Sachio*; Ogiyanagi, Jin; Chimi, Yasuhiro; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*
no journal, ,
no abstracts in English
Ogiyanagi, Jin; Chimi, Yasuhiro; Shimada, Sachio*; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*
no journal, ,
no abstracts in English
