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134 results on '"Hinoki, Tatsuya"'

21. Effect of BN nanoparticle content in SiC matrix on microstructure and mechanical properties of SiC/SiC composites.

Author

Shimoda, Kazuya and Hinoki, Tatsuya

Subjects
*NANOPARTICLES, *TENSILE strength, *MICROSTRUCTURE, *BENDING strength
Abstract

BN‐nanoparticle‐containing SiC‐matrix‐based composites comprising SiC fibers and lacking a fiber/matrix interface (SiC/BN + SiC composites) were fabricated by spark plasma sintering (SPS) at 1800°C for 10 min under 50 MPa in Ar. The content of added BN nanoparticles was varied from 0 to 50 vol.%. The mechanical properties of the SiC/BN + SiC composites were investigated thoroughly. The SiC/BN + SiC composites with a BN nanoparticle content of 50 vol.%, which had a bulk density of 2.73 g/cm3 and an open porosity of 5.8%, exhibited quasiductile fracture behavior, as indicated by a short nonlinear region and significantly shorter fiber pullouts owing to the relatively high modulus. The composites also exhibited high strength as well as bending, proportional limit stress, and ultimate tensile strength values of 496 ± 13, 251 ± 30, and 301 MPa ± 56 MPa, respectively, under ambient conditions. The SiC fibers with contents of BN nanoparticles above 30 vol.% were not severely damaged during SPS and adhered to the matrix to form a relatively weak fiber/matrix interface. [ABSTRACT FROM AUTHOR]

Published
2023
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47. Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa.

Author

Ishibashi, Ryo, Hayashi, Yasunori, Bo, Huang, Kondo, Takao, and Hinoki, Tatsuya

Subjects
SILICON carbide, ZIRCALOY-2, IRRADIATION, TRANSMISSION electron microscopy, RADIATION, POINT defects, IONS
Abstract

Replacement of conventional Zircaloy fuel cladding with silicon carbide (SiC) fuel cladding is expected to significantly decrease the amount of hydrogen generated from fuel claddings by the reaction with steam during severe accidents. One of their critical issues addressed regarding practical application has been hydrothermal corrosion. Thus, the corrosion resistant coating technology using a Ti-Cr multilayer was developed to suppress silica dissolution from SiC fuel cladding into reactor coolant under normal operation. The effect of radiation on adhesion of the coating to SiC substrate and its microstructure characteristics were investigated following Si ion irradiation at 573 K up to 3 dpa for SiC. Measurement of swelling in pure Ti, pure Cr and SiC revealed that the maximum inner stress attributed to the swelling difference was generated between the coating and SiC substrate by irradiation of 1 dpa. No delamination and cracking were observed in cross-sectional specimens of the coated SiC irradiated up to 3 dpa. According to analyses using transmission electron microscopy, large void formation and cascade mixing due to irradiation were not observed in the coating. The swelling in the coating at 573 K was presumed to be caused by another mechanism during radiation such as point defects rather than void formation. [ABSTRACT FROM AUTHOR]

Published
2022
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48. Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond

Author

Nozawa, Takashi, Ozawa, Kazumi, Park, ChangHo, Park, Joon-Soo, Kohyama, Akira, Hasegawa, Akira, Nogami, Shuhei, Hinoki, Tatsuya, Kondo, Sosuke, Yano, Toyohiko, Shibayama, Tamaki, Tsuchiya, Bun, Shikama, Tatsuo, Nagata, Shinji, Tanaka, Teruya, Iwakiri, Hirotomo, Yamamoto, Yasushi, Konishi, Satoshi, Kasada, Ryuta, Kondo, Masatoshi, Kunugi, Tomoaki, Yokomine, Takehiko, Ueki, Yoshitaka, Okubo, Nariaki, Taguchi, Tomitsugu, and Tanigawa, Hiroyasu

Abstract

The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the application of SiC/SiC composites as functional structure to be used in the dual coolant breeding blanket concept. This paper aims to summarize previous 10-years activities of the R&D of Japan and to provide the key deliverables toward the DEMO design. In Task-1, good creep and fatigue durability were first demonstrated. Besides, in-plane and inter-laminar strength anisotropy maps at elevated temperatures were comprehensively identified. In parallel, the irradiation effects of SiC materials were specifically determined as input parameters of the analytical model to provide for the irradiation-induced residual stresses. In Task-2, the apparent dose-dependence of the radiation-induced electrical conductivity and the indicative radiation-induced electrical degradation was identified by various irradiation sources. In addition, good gas confinement was identified. Furthermore, no accelerated corrosion for duration of 3000 h at below 1173 K was first demonstrated. With these achievements, it is suggested that the in-vessel component technology, e.g., material corrosion database development, activated corrosion product evaluation code development, compact module tests for validation of the key functions of the components, technology integration assessment for fusion nuclear tests, etc., should be further developed toward DEMO in near-term.

Published
2018

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