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Yano, Yasuhide; Hashidate, Ryuta; Tanno, Takashi; Imagawa, Yuya; Kato, Shoichi; Onizawa, Takashi; Ito, Chikara; Uwaba, Tomoyuki; Otsuka, Satoshi; Kaito, Takeji
JAEA-Data/Code 2021-015, 64 Pages, 2022/01
JAEA-Data-Code-2021-015.pdf:2.6MB
From a view point of practical application of fast breeder reactor cycles, which takes advantage of safety and economic efficiency and makes a contribution of volume reduction and mitigation of degree of harmfulness of high-level radioactive waste, it is necessary to develop fuel cladding materials for fast reactors (FRs) in order to achieve high-burnup. Oxide dispersion strengthened (ODS) steel have been studied for use as potential fuel cladding materials in FRs owing to their excellent resistance to swelling and their high-temperature strength in Japan Atomic Energy Agency. It is very important to establish the materials strength standard in order to apply ODS steels as a fuel cladding. Therefore, it is necessary to acquire the mechanical properties such as tensile, creep rupture strength tests and so on. In this study, tensile and creep rupture strengths of 9Cr-ODS steel claddings were evaluated using by acquired these data. Because of the phase transformation temperature of 9Cr-ODS steel, temperature range for the evaluation was divided into two ones at AC1 transformation temperature of 850
C.
Tanno, Takashi; Yano, Yasuhide; Oka, Hiroshi; Otsuka, Satoshi; Uwaba, Tomoyuki; Kaito, Takeji
Nuclear Materials and Energy (Internet), 9, p.353 - 359, 2016/12
Times Cited Count：9 Percentile：64.88(Nuclear Science & Technology)Materials for core components of fusion reactors and fast reactors, such as blankets and fuel cladding tubes, must be excellent in high temperature strength and irradiation resistance because they will be exposed to high heat flux and heavy neutron irradiation. Oxide dispersion strengthened (ODS) steels have been developing as the candidate material. Japan Atomic Energy Agency (JAEA) have been developing 9 and 11 Chromium (Cr) ODS steels for advanced fast reactor cladding tubes. The JAEA 11Cr-ODS steels were rolled in order to evaluate their anisotropy. Tensile tests and creep tests of them were carried out at 700 C in longitudinal and transverse orientation. The anisotropy of tensile strength was negligible, though that of creep strength was distinct. The observation results and chemical composition analysis suggested that the cause of the anisotropy in creep strength was prior powder boundary including Ti-rich precipitates.
Mizuta, Shunji; ;
JNC TN9400 2000-048, 28 Pages, 2000/04
JNC-TN9400-2000-048.pdf:0.64MB
ODS (Oxide Dispersion Strengthened) ferritic-martainsitic steels are one of the most prospective cladding materials for advanced fast breeder reactors, since they are expected to have excellent swelling resistance and superior high temperature strength due to the finely distributed stable oxide particles(Y
O
). Properties and the tentative strength equations for ODS ferritic-martainsitic were proposed on the basis of the latest data to apply to the feasibility study of the sodium coolant MOX fuel plant. The items of equations are follows. (1)creep rupture strength (2)correction factor of creep rupture strength (in Na and in reactor) (3)outer surface eorrosion (Na) (4)inner surface corrosion (in MOX fuel pin) (5)thermal conductivity
Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;
JAERI-Tech 99-024, 65 Pages, 1999/03
no abstracts in English
Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;
JAERI-Tech 98-010, 107 Pages, 1998/03
no abstracts in English
Hishinuma, Akimichi; *; *; *
Physica Status Solidi, 160(2), p.431 - 440, 1997/00
no abstracts in English
Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *
Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00
no abstracts in English
Tsutagi, Koichi; Seki, Masayuki; Tobita, Noriyuki; Nagai, Shuichiro; ; *; *
PNC TN8410 91-256, 64 Pages, 1991/05
None
; Hada, Kazuhiko; Koikegami, Hajime*; *
Nihon Genshiryoku Gakkai-Shi, 33(5), p.475 - 481, 1991/05
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Watanabe, Katsutoshi; Nakajima, Hajime; Sahira, Kensho*; *; Takeiri, Toshiki*; Saito, Teiichiro*; Takatsu, Tamao*; Nakanishi, Tsuneo*
JAERI-M 89-206, 120 Pages, 1989/12
no abstracts in English
*; *; *; *; *; *
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.265 - 273, 1988/00
no abstracts in English
; Ueda, Shuzo
Atsuryoku Gijutsu, 24(5), p.254 - 263, 1986/00
no abstracts in English
Kondo, Tatsuo; Nakajima, Hajime; *; ; *; *
Proc.of Int.Conf.on Irradiation Behaviour of Metallic Materials for Fast Reactor Core Components, 6 Pages, 1979/00
no abstracts in English
Oka, Hiroshi*; Hashimoto, Naoyuki*; Tanno, Takashi; Yano, Yasuhide; Otsuka, Satoshi; Kaito, Takeji
no journal, ,
The effect of nitrogen concentration on microstructure and high temperature creep strength of 9Cr-ODS ferritic/martensitic steel was investigated. The results showed that the tensile strength and high temperature creep strength decreased with increasing nitrogen concentration. The microstructural analysis suggests that the non-uniform dispersion of Y-Ti-O particles due to the increase in nitrogen concentration may have been the cause of the decrease in high temperature creep strength. The non-uniform dispersion of Y-Ti-O particles is probably the result of the consumption of Ti by the formation of Ti nitrides, which weakened its refinement effect on the nano-sized oxide particles.
