Hideo Sakasegawa
Japan Atomic Energy Agency
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Featured researches published by Hideo Sakasegawa.
Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2013
Manabu Tamura; Fujio Abe; K. Shiba; Hideo Sakasegawa; Hiroyasu Tanigawa
Long-term rupture data for 79 types of heat-resistant steels including carbon steel, low-alloy steel, high-alloy steel, austenitic stainless steel, and superalloy were analyzed, and a constant for the Larson–Miller (LM) parameter was obtained in the current study for each material. The calculated LM constant, C, is approximately 20 for heat-resistant steels and alloys except for high-alloy martensitic steels with high creep resistance, for which
Journal of Nuclear Science and Technology | 2011
Shuhei Nogami; Takamoto Itoh; Hideo Sakasegawa; Hiroyasu Tanigawa; Eichi Wakai; A. Nishimura; Akira Hasegawa
Journal of Nuclear Science and Technology | 2014
Hideo Sakasegawa; Hiroyasu Tanigawa; Masami Ando
C \approx 30
Journal of Nuclear Science and Technology | 2018
Hideo Sakasegawa; Hiroyasu Tanigawa; Dai Hamaguchi
Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2009
Shigeharu Ukai; Satoshi Ohtsuka; Takeji Kaito; Hideo Sakasegawa; N. Chikata; Shigenari Hayashi; S. Ohnuki
. The apparent activation energy was also calculated, and the LM constant was found to be proportional to the apparent activation energy with a high correlation coefficient, which suggests that the LM constant is a material constant possessing intrinsic physical meaning. The contribution of the entropy change to the LM constant is not small, especially for several martensitic steels with large values of C. Deformation of such martensitic steels should accompany a large entropy change of 10 times the gas constant at least, besides the entropy change due to self-diffusion.
Journal of Nuclear Materials | 2007
Satoshi Ohtsuka; Shigeharu Ukai; Hideo Sakasegawa; Masayuki Fujiwara; Takeji Kaito; Takeshi Narita
The effect of specimen size and shape on the fatigue life of reduced activation ferritic/martensitic steel “F82H IEA-heat” was investigated to develop a fatigue life evaluation method using a small specimen for testing neutron-irradiated materials. The fatigue test was carried out at room temperature in air using three kinds of round-bar specimen (minimum diameter cross sections of 1, 4, and 7 mm) and one hourglass specimen (minimum diameter cross section of 1.25 mm). The effect of specimen size on fatigue life from a level of 103 to 104 cycles was almost negligible for the round-bar specimens. The shorter fatigue life at the total strain range below 0.6% and the slightly longer fatigue life at the total strain range above 0.8% of the hourglass specimen relative to that of the standard specimen were observed from a level of 102 to 104 cycles.
Journal of Alloys and Compounds | 2008
Hideo Sakasegawa; Manabu Tamura; Satoshi Ohtsuka; Shigeharu Ukai; Hiroyasu Tanigawa; Akira Kohyama; Masayuki Fujiwara
Oxide-dispersion-strengthened (ODS) steels are attractive materials for application as fuel cladding in fast reactors and first-wall material of fusion blanket. Recent studies have focused more on high-chromium ferritic (12–18 wt% Cr) ODS steels with attractive corrosion resistance properties. However, they have poor material workability, require complicated heat treatments for recrystallization, and possess anisotropic microstructures and mechanical properties. On the other hand, low-chromium ferritic/martensitic (8–9 wt% Cr) ODS steels have no such limitations; nonetheless, they have poor corrosion resistance properties. In our work, we developed a corrosion-resistant coating technique for a low-chromium ferritic/martensitic ODS steel. The ODS steel was coated with the 304 or 430 stainless steel, which has better corrosion resistances than the low-chromium ferritic/martensitic ODS steels. The 304 or 430 stainless steel was coated by changing the canning material from mild steel to stainless steel in the conventional material processing procedure for ODS steels. Microstructural observations and micro-hardness tests proved that the stainless steels were successfully coated without causing a deterioration in the mechanical property of the low-chromium ferritic/martensitic ODS steel.
Fusion Engineering and Design | 2011
Hiroyasu Tanigawa; K. Shiba; Hideo Sakasegawa; Takanori Hirose; S. Jitsukawa
ABSTRACT Reduced activation ferritic/martensitic steels (RAFMs) have been developed for the structural material of fusion reactor blanket. Extensive researches were conducted using transmission electron microscopy (TEM) to define the precipitation behavior of MX (M: Metallic elements, X: C and/or N) precipitates such as vanadium and tantalum carbides and/or nitrides, since they strongly affect material properties. However, it is not completely defined yet. TEM can obtain detailed information, but the observable volume is limited and it needs a long time to obtain representative and statistically reliable microstructural information. It is fruitful to complement TEM results applying other characterization techniques together. In this work, we studied the precipitation behavior of MX in the RAFM, F82H, through the application of various techniques with larger observable volumes and compared with TEM past results. We additionally tried to find sub-nanometric MX precipitates that can be hardly observed through TEM. From the result, the TaX (X: C and/or N) phase surely varied depending on the chemical composition of alloy and heat treatment; some TaX precipitates were unstable during tempering, MX precipitates were intergranular, and sub-nanometric MX were not found in the matrix. These obtained results were helpful to define the precipitation behavior of MX in F82H.
Journal of Nuclear Materials | 2007
Hiroyasu Tanigawa; Hideo Sakasegawa; H. Ogiwara; Hirotatsu Kishimoto; Akira Kohyama
Journal of Nuclear Materials | 2008
Hideo Sakasegawa; Shigeharu Ukai; Manabu Tamura; Satoshi Ohtsuka; Hiroyasu Tanigawa; Hiroyuki Ogiwara; Akira Kohyama; Masayuki Fujiwara