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Journal Articles

Manufacturability and strength assessment of modified 9Cr-1Mo steel products for Japan sodium cooled fast reactor components, 1; Forging with large thickness

Nagae, Yuji; Enuma, Yasuhiro*; Oshikiri, Masato*; Date, Shingo*; Toyoshi, Akira*; Aizawa, Taiki*; Koyama, Yoichi*; Yanagisawa, Yusuke*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2), p.161 - 169, 2011/07

no abstracts in English

Journal Articles

Prediction of creep-fatigue life based on fracture energy in modified 9Cr-1Mo steel

Nagae, Yuji

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2), p.125 - 134, 2011/07

no abstracts in English

Journal Articles

Manufacturability and strength assessment of modified 9Cr-1Mo steel products for Japan sodium cooled fast reactor components, 2; Long thin-walled tubes with small diameter

Wakai, Takashi; Onizawa, Takashi; Obara, Satoshi; Nakashima, Takashi*; Yokoyama, Tetsuo*; Iseda, Atsuro*; Ogumo, Shinya*; Futagami, Satoshi*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2), p.171 - 181, 2011/07

To enhance the economic competitiveness, high-Cr ferritic steels are adopted as the structural materials for JSFR, because the steels have both excellent high temperature strength and thermal properties. Among the high-Cr ferritic steels, modified 9Cr-1Mo steel (compatible to ASTM A213 T91) is a candidate of the structural material for the demonstration facility of JSFR, because the steel has superior microstructure stability at elevated temperature for long time. As for the steam generator tubes, to enhance the safety, straight double-walled tubes will be employed. In this study, the following technical issues were investigated; (1) Industrial manufacturability of thin-walled small bore tubes made of modified 9Cr-1Mo steel, (2) performance demonstration of the thin-walled small bore tubes, (3) industrial manufacturability of double-walled tubes using the thin-walled small bore tubes and (4) extraction of technical problems to manufacture the double-walled tubes for the JSFR steam generator. As a result, thin-walled small bore tubes made of modified 9Cr-1Mo steel were successfully manufactured by using the existing industrial facilities, up to 17m in length. The mechanical properties of the tubes satisfy the requirements from plant designing, as well as those from the material strength standards. Further, double walled tubes were also manufactured, up to 15m in length. The surface conditions of the tubes and the contact pressure between inner and outer tubes should be optimized.

Journal Articles

The Creep rupture strength evaluation in welded joint of Mod.9Cr-1Mo steel

Wakai, Takashi; Nagae, Yuji; Takaya, Shigeru; Obara, Satoshi; Date, Shingo*; Yamamoto, Kenji*; Kikuchi, Koichi*; Sato, Kenichiro*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2), p.147 - 159, 2011/07

By employing high-Cr ferritic steels to the structural materials for JSFR, a compact plant designing can be achieved. It contributes to reduce the construction cost and to enhance the freedom of designing. Among the high-Cr ferritic steels, modified 9Cr-1Mo steel (compatible to ASTM A335 P91) is a candidate of the structural material for the demonstration facility of JSFR, because the steel has superior microstructure stability at elevated temperature for long time. However, remarkable creep strength degradation has been observed in the welded joint of high-Cr ferritic steels, especially in long-term region. It is known as "Type-IV damage". In the elevated temperature designing for the fast reactors, such creep strength degradation must be taken into account properly. Therefore, the creep strength assessment procedure and the allowable stress for the welded joints made of modified 9Cr-1Mo steel have been proposed. In this study, (1) a series of creep rupture tests to verify the validity of the creep strength assessment procedure was performed. (2) Applicability of the creep strength assessment procedure to the creep fatigue strength assessment of the welded joints made of modified 9Cr-1Mo steel was investigated. (3) Metallurgical examinations of creep ruptured specimens were carried out to confirm the contribution of "Type-IV damage". As a result, it was demonstrated that the creep strength assessment procedure was validated using the long-term creep rupture test results less than 30,000h and that the creep strength assessment procedure was applicable to the creep-fatigue strength assessment based on some uniaxial creep-fatigue test results.

Journal Articles

Creep life evaluation of high Cr ferritic steels in terms of omega-method and effects of V and Nb on the omega-parameters

Yoshida, Yu*; Mitsuhara, Masatoshi*; Ikeda, Kenichi*; Nakashima, Hideharu*; Wakai, Takashi

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 47(10), p.109 - 113, 2006/07

This paper studies the influence of V and Nb on the creep strength and behavior of high Cr ferritic steels. A series of creep tests of 11 steels having various V and Nb contents is conducted. The test results are analyzed by omega-method and the microstructures of the damaged specimens are examined by EBSP. As a result, it is shown that omega-method gives good prediction of creep lives of the steels and that the influence of V and Nb on the omega-parameters is significant. In addition, it is clarified that the martensitic microstructure of the steels depends upon Nb content.

Journal Articles

Long-term creep and rupture behavior of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

Kurata, Yuji; *; ; Shindo, Masami; Nakajima, Hajime; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 36(2), p.149 - 156, 1995/07

no abstracts in English

Journal Articles

Development of hastelloy alloy XR filler metal lowered weld cracking susceptibility

Watanabe, Katsutoshi; Nakajima, Hajime; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*; Saito, Teiichiro*; Takatsu, Tamao*; Nakanishi, Tsuneo*; Koikegami, Hajime*; Higuchi, Makoto*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 33(2), p.227 - 242, 1992/00

no abstracts in English

Journal Articles

Electrochemical evaluation of thermal aging embrittlement of 21/4Cr-1Mo steel for the pressure vessel of High Temperature Engineering Test Reactor

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 32(2), p.169 - 175, 1991/00

no abstracts in English

Journal Articles

Effect of carburizing helium environment on creep properties of hastelloy XR

Kurata, Yuji; *; Nakajima, Hajime

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.109 - 120, 1988/00

no abstracts in English

Journal Articles

Effect of decarburizing helium environment on creep properties of hastelloy XR

Kurata, Yuji; *; Nakajima, Hajime

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.97 - 107, 1988/00

no abstracts in English

Journal Articles

Mechanism on low temperature sensitization of metastable austenitic stainless steels

Kiuchi, Kiyoshi; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.177 - 188, 1988/00

no abstracts in English

Journal Articles

Effects of alloying elements on reliability under heat flux of stainless steels

Kiuchi, Kiyoshi; B.Harald*; ; Seki, Masahiro; Araki, Masanori

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.189 - 197, 1988/00

no abstracts in English

Journal Articles

Mechanism of void swelling and development of SAR alloy with high irradiation resistance

Kiuchi, Kiyoshi; ; Hishinuma, Akimichi

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.231 - 239, 1988/00

no abstracts in English

Journal Articles

Effect of Cr phase on high temperature creep resistance of a 30Cr-50Ni-2Mo alloy

*; *; *; *; *; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.265 - 273, 1988/00

no abstracts in English

Journal Articles

Influence of grain size and solution heat treatment temperature on creep properties of Hastelloy XR

Kurata, Yuji; Ogawa, Yutaka

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 28(2), p.213 - 220, 1987/00

no abstracts in English

Journal Articles

The Effect of the improvement of corrosion resistance on high temperature creep of Ni-base superalloy in helium environment.

; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(1), p.49 - 58, 1979/00

no abstracts in English

Journal Articles

Corrosion of NiCr Binary Alloys in VHTR-He

*; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(1), p.93 - 102, 1979/00

no abstracts in English

Journal Articles

Ductility loss of neutron irradiated Ni base heat resistant alloys at elevated temperatures

; Ogawa, Yutaka; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(3), p.283 - 290, 1979/00

no abstracts in English

Journal Articles

Optimization of austenitic steels for LMFBR applications, Pt.2; Experimental evaluation of alloys

Nakajima, Hajime; *; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(2), p.195 - 211, 1979/00

no abstracts in English

Journal Articles

Effect of Mn on oxidation resistance of hastelloy-x in the simulated VHTR helium environment.

Shindo, Masami; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 19(3), p.331 - 338, 1978/00

no abstracts in English

22 (Records 1-20 displayed on this page)