Takashi Otomo
Japan Atomic Energy Research Institute
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Featured researches published by Takashi Otomo.
Journal of Nuclear Science and Technology | 2003
Fumihisa Nagase; Takashi Otomo; Hiroshi Uetsuka
Isothermal oxidation tests in flowing steam were performed on low-Sn Zircaloy-4 cladding tubes over the wide temperature range from 773 to 1,573 K in order to obtain oxidation kinetics applicable to various loss-of-coolant accident conditions of LWRs. The oxidation generally obeys a parabolic rate law for the examined time range up to 3,600 s at temperatures from 1,273 to 1,573 K, and for a limited time range up to 900 s from 773 to 1,253 K. A cubic rate law is preferable for evaluating the longer-term oxidation at 1,253 K and below. The parabolic rate law constant and the cubic rate law constant for measured weight gain were evaluated at every examined temperature, and Arrhenius-type equations were determined in order to describe the temperature dependence of the rate constants. It was indicated that the change of the oxidation kinetics from the cubic to the parabolic rate and the discontinuities in the temperature dependence of the rate constants are caused by the monoclinic/tetragonal phase structure change of ZrO2.
Journal of Nuclear Materials | 1997
Fumihisa Nagase; Hiroshi Uetsuka; Takashi Otomo
Abstract With a view to investigating the chemical interactions between B 4 C and type 304 stainless steel, the reaction couples ofthese two materials were isothermally annealed in the temperature range between 1073 and 1623 K. As a result of the chemical interactions, complicated reaction layers were formed at the interface of the reaction couple. To evaluate the reaction kinetics, the decrease in the thickness of stainless steel and the reaction layer growth were measured as a function of temperature and time. The overall reaction generally obeyed the parabolic rate law. Both a parabolic rate law constant and an apparent activation energy were determined. A discontinuity in the temperature dependence of the parabolic rate constants was found in the temperature range between 1473 and 1498 K. This corresponds to the formation of the liquid phase at the reaction interface.
Journal of Nuclear Materials | 1993
Jinichi Nakamura; Masao Hashimoto; Takashi Otomo; Satoru Kawasaki
Abstract The effects of oxygen partial pressure on the oxidation of Zircaloy-4 were examined at 773 K under the oxygen partial pressure between 0.1 and 2 × 10−5MPa to study the oxidation behavior of spent fuel during dry storage. The oxidation rate at first obeyed a cubic rate law, and changed to obey a linear rate law at almost the same weight gains even at different oxygen partial pressures. The oxidation rate during posttransition period showed pO20.15 dependence. The dependency of the oxidation rate in the posttransition region agreed with the results of the oxygen diffusion coefficient in zirconium oxide measured by Keneshea and Douglass. Degradation of the protective oxide film of Zircaloy-4 under low oxygen partial pressures was not observed within the oxygen partial pressure range examined. The results of this experiment showed that the oxidation rate in air can be adopted to estimate the cladding oxidation rate during dry fuel storage in air and under low oxygen partial pressures.
Journal of Nuclear Materials | 1997
Hiroshi Uetsuka; Fumihisa Nagase; Takashi Otomo
Abstract The chemical interactions between Zircaloy-4 and Inconel-718 were investigated in the temperature range from 1223 to 1523 K. Multiple layers were formed at the interface of the reaction couple. The reaction generally obeyed a parabolic rate law and the rate of the reaction was determined at each examined temperature. It increased with the temperature increase. The discontinuity in the temperature dependence of the reaction rate was found at two temperatures, at about 1240 K and 1450 K. The elemental analysis with an SEM/EDX indicated that the discontinuities corresponded to the change of the reaction mechanism.
Journal of Nuclear Science and Technology | 1983
Satoru Kawasaki; Masao Hashimoto; Takashi Otomo; Teruo Furuta; Hiroshi Uetsuka
In order to study the effect of burst temperature on the coolant flow channel restriction, burst tests of fuel bundles were performed. Each bundle consisted of 49 rods (7×7 rods), and bursts were conducted in flowing steam. Burst temperature was changed by changing the internal gas pressure in rods. After the burst, the ballooning behavior of each rod and the degree of coolant flow area restriction in the bundle were measured. Maximum swelling of rod occurs when the burst temperature is around α and α+β phase boundary, and this phenomenon is almost the same as that in single rod burst tests. Maximum coolant flow area restriction is also observed in this condition.
Journal of Nuclear Science and Technology | 1989
Hiroshi Uetsuka; Takashi Otomo
Journal of Nuclear Science and Technology | 1978
Teruo Furuta; Satoru Kawasaki; Masao Hashimoto; Takashi Otomo
Journal of Nuclear Science and Technology | 1993
Jinichi Nakamura; Takashi Otomo; Satoru Kawasaki
Journal of Nuclear Science and Technology | 1997
Fumihisa Nagase; Hiroshi Uetsuka; Takashi Otomo
Transactions of the American Nuclear Society | 1993
H. Uetsuka; F. Nagase; Takashi Otomo