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Journal Articles

Oxide dispersion strengthened steels

Ukai, Shigeharu*; Ono, Naoko*; Otsuka, Satoshi

Comprehensive Nuclear Materials, 2nd Edition, Vol.3, p.255 - 292, 2020/08

Fe-Cr-based oxide dispersion strengthened (ODS) steels have a strong potential for high burnup (long-life) and high-temperature applications typical for SFR fuel cladding. Current progress in the development of Fe-Cr-based ODS steel claddings is reviewed, including their relevant mechanical properties, e.g. tensile and creep rupture strengths in the hoop directions. In addition, this paper reviewed the current research status on corrosion resistant Fe-Cr-Al-based ODS steel claddings, which are greatly paid attention recently as the accident tolerant fuel claddings for the light water reactor (LWR) and also as the claddings of the lead fast reactors (LFR) utilizing Pb-Bi eutectic (LBE) coolant.

Journal Articles

Development of ODS tempered martensitic steel for high burn up fuel cladding tube of SFR

Otsuka, Satoshi; Tanno, Takashi; Oka, Hiroshi; Yano, Yasuhide; Tachi, Yoshiaki; Kaito, Takeji; Hashidate, Ryuta; Kato, Shoichi; Furukawa, Tomohiro; Ito, Chikara; et al.

2018 GIF Symposium Proceedings (Internet), p.305 - 314, 2020/05

Oxide Dispersion Strengthened (ODS) steel has been developed worldwide as a high-strength and radiation-tolerant steel used for advanced nuclear system. Japan Atomic Energy Agency (JAEA) has been developing ODS steel as the primary candidate material of Sodium cooled Fast Reactor (SFR) high burn-up fuel cladding tube. Application of high burn-up fuel to SFR core can contribute to improvement of economical performance of SFR in conjunction with volume and hazardousness reduction of radioactive waste. This paper described the current status and future prospects of ODS tempered martensitic steel development in JAEA for SFR fuel application.

Journal Articles

Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors

Ukai, Shigeharu*; Otsuka, Satoshi; Kaito, Takeji; de Carlan, Y.*; Ribis, J.*; Malaplate, J.*

Structural Materials for Generation IV Nuclear Reactors, p.357 - 414, 2017/00

 Times Cited Count:24 Percentile:1.33

Oxide dispersion strengthened (ODS) steels are the most promising candidate materials for fuel cladding of generation IV nuclear reactors. The progress and current status for development of ODS/FM(ferrite-martensite) steels conducted mainly in Japan and France are overviewed. The chemical compositions of ODS/FM steels are listed. Fabrication routes of cladding tube are mentioned for ferrite-type ODS steels using recrystallized process and martensite-type one using $$alpha$$-$$gamma$$ phase transformation. The optimized process is identical for both countries. Joining process between cladding and end-plug has been also developed by using the pressurized resistance upset welding method. The improvements brought by ODS/FM steels in high-temperature strength and irradiation resistance are verified.

Oral presentation

Structure stability of ferritic ODS steel for fast reactor fuel cladding tube under irradiation

Tanno, Takashi; Oka, Hiroshi; Yano, Yasuhide; Otsuka, Satoshi; Kaito, Takeji

no journal, , 

Fe self-ion irradiation to ODS steels was conducted at 400$$^{circ}$$C to evaluate the stability of oxide nano-dispersoids in the ODS steels and embrittlement behavior of higher Cr ODS steel under irradiation. Fe and He dual ion irradiation test at 470$$^{circ}$$C was also conducted to evaluate the influence of He existence. The indentation hardness increased in early stage of the irradiation, and decreased over 150 dpa. But the hardness was higher than that as unirradiated, even if the dose reached 230 dpa. The Cr enrichment from 9Cr to 11Cr would not lead to extra irradiation hardening and/or irradiation embrittlement because the irradiation hardening behavior of 9Cr and 11Cr-ODS steels were almost same. The irradiation hardening due to Fe+He dual ions irradiation was negligible or comparatively small. Therefore it was considered that fine and dense voids formation enhanced by He existence was not significant.

Oral presentation

Influence of impurity nitrogen on microstructure and high-temperature strength of 9Cr-ODS steel

Oka, Hiroshi; Tanno, Takashi; Otsuka, Satoshi; Kaito, Takeji

no journal, , 

no abstracts in English

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