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Dive into the research topics where Yasuhiro Ishijima is active.

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Featured researches published by Yasuhiro Ishijima.


Journal of Nuclear Science and Technology | 2016

The effect of crystal textures on the anodic oxidization of zirconium in a boiling nitric acid solution

Chiaki Kato; Yasuhiro Ishijima; Fumiyoshi Ueno; Masahiro Yamamoto

ABSTRACT The effects of crystal textures and the potentials in the anodic oxidation of zirconium in a boiling nitric acid solution were investigated to study the stress corrosion cracking of zirconium in nitric acid solutions. The test specimen was machined such that the specimen surface was parallel to the rolling surface, arranged with a (0002) crystal texture. The potentials applied for the anodic oxidation of zirconium were set at 1.2, 1.4, and 1.5 V against a saturated KCl–Ag/AgCl electrode (SSE) in boiling 6 M HNO3. The growth of the zirconium oxide film dramatically changed depending on the applied potential at a closed depassivation potential (1.47 V vs. SSE in this study). At 1.5 V, the zirconium oxide film rapidly grows, and its growth exhibits cyclic oxidation kinetics in accordance with a nearly cubic rate law. The zirconium oxide film grows according to the quantity of electric charge and the growth rate does not depend on the crystal texture in the pretransition region before the cyclic oxidation kinetics. However, the growth and cracking under the thick oxide film depend on the crystal texture in the transition region. On the normal direction side, the oxide film thickness decreases on average since some areas of the thick oxide film are separated from the specimen surface owing to the cracks in the thick oxide. On the rolling direction (RD) side, no cracks in the thick oxide film are observed, but cracks are found under the thick oxide film, which deeply propagate in metal matrix along the RD without an external stress. The cracks under the thick oxide film propagate to the center of the oxide layer. The crystal orientation relationship between the oxide layer and the zirconium matrix is (0002)Zr//(111)ZrO2, and the cracks in the oxide layer propagate in the (0002)Zr plane in the zirconium matrix. The oxide layer consists of string-like zirconium oxide and zirconium hydride. The string-like zirconium oxide contains orthorhombic ZrO2 in addition to monoclinic ZrO2. It is not well known why the cracks propagate along the (0002)Zr plane under the thick oxide film. As one assumption for the mechanism of crack initiation and propagation without an external stress, it is considered that the oxidizing zirconium hydrides precipitated in the (0002)Zr plane near the interface of the thick oxide film and the matrix. Then, the phase transformation from orthorhombic ZrO2 to monoclinic ZrO2 in the oxide layer causes the crack propagation in the (0002) plane.


Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications | 2013

Hydrogen Absorption Behavior of Titanium Alloys by Cathodic Polarization

Yasuhiro Ishijima; Takafumi Motooka; Fumiyoshi Ueno; Masahiro Yamamoto; Gunzo Uchiyama; Jun’ichi Sakai; Ken’ichi Yokoyama; Eiji Tada; Tooru Tsuru; Yasuo Nojima; Sachio Fujine

Titanium and Ti-5mass%Ta alloy has been utilized in nuclear fuel reprocessing plant material because of its superior corrosion resistance in nitric acid solutions. However, Ti alloy have been known to high susceptibility of hydrogen embrittlement. To evaluate properties of hydrogen absorption and hydrogen embrittlement of Ti alloys, cathodic polarization tests and slow strain rate tests (SSRT) under cathodic polarization were carried out. Results show titanium hydrides covered on the surface of metals and hydrides thickness were within 10μm. But hydride did not observed at inner part of metals. Ti and Ti-5%Ta did not show hydrogen embrittlement by SSRT under cathodic charging. These results suggested that Ti and Ti-5%Ta could absorb hydrogen. But hydrogen did not penetrate inner portion of the metals more than 10μm in depth because titanium hydrides act as barrier of hydrogen diffusion. It is considered that retardation of hydrogen diffusion hindered hydrogen embrittlement of Ti and Ti-5%Ta alloys.Copyright


Journal of Nuclear Materials | 2011

Radiation hardening and IASCC susceptibility of extra high purity austenitic stainless steel

Ikuo Ioka; Yasuhiro Ishijima; Kouji Usami; Naotoshi Sakuraba; Y. Kato; Kiyoshi Kiuchi


Materials Transactions | 2013

Stress Corrosion Cracking Behavior of Zirconium in Boiling Nitric Acid Solutions at Oxide Formation Potentials

Yasuhiro Ishijima; Chiaki Kato; Takafumi Motooka; Masahiro Yamamoto; Yoichi Kano; Tetsunari Ebina


Zairyo-to-kankyo | 2012

Effect of Creep on Susceptibility to Stress Corrosion Cracking of Zirconium in the Simulated Spent Nuclear Fuel Solution

Chiaki Kato; Yasuhiro Ishijima; Masahiro Yamamoto


Atomic Energy Society of Japan | 2017

Hydrogen Absorption Behavior on Zirconium under γ-Radiolysis of Nitric Acid Solution

Yasuhiro Ishijima; Fumiyoshi Ueno; Hitoshi Abe


The Proceedings of the International Conference on Nuclear Engineering (ICONE) | 2015

ICONE23-2026 THERMAL AGING EFFECT FOR CREEP PROPERTIES ON NI BASE REFRACTORY ALLOYS

Yasuhiro Ishijima; Fumiyoshi Ueno


Corrosion engineering | 2013

Reduction Mechanism of Nitrate on Titanium

Atsushi Komatsu; Yasuhiro Ishijima; Takafumi Motooka; Fumiyoshi Ueno; Masahiro Yamamnto


JOURNAL OF HIGH PRESSURE INSTITUTE OF JAPAN | 2009

Evaluation method of thermal deformation for Fast Spectrum Light Water Reactor (FLWR)

Yasuhiro Ishijima; Ikuo Ioka; Kiyoshi Kiuchi; Tetsuji Kaneko; Tsutomu Okubo; Masahiro Yamamoto


214th ECS Meeting | 2009

Stress Corrosion Cracking of Zirconium in Boiling Nitric Acid Solution at Potentiostatic Condition

Masahiro Yamamoto; Chiaki Kato; Yasuhiro Ishijima; Youichi Kano; Tetsunari Ebina

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Chiaki Kato

Japan Atomic Energy Research Institute

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Fumiyoshi Ueno

Japan Atomic Energy Agency

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Takafumi Motooka

Japan Atomic Energy Agency

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Ikuo Ioka

Japan Atomic Energy Agency

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Kiyoshi Kiuchi

Japan Atomic Energy Agency

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Atsushi Komatsu

Japan Atomic Energy Agency

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Eiji Tada

Tokyo Institute of Technology

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Gunzo Uchiyama

Japan Atomic Energy Agency

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Hitoshi Abe

Graduate University for Advanced Studies

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