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Journal Articles

Mechanical properties of full austenitic welding joint at cryogenic temperature for the ITER toroidal field coil structure

Iguchi, Masahide; Saito, Toru; Kawano, Katsumi; Chida, Yutaka; Nakajima, Hideo; Ogawa, Tsuyoshi*; Katayama, Yoshinori*; Ogata, Hiroshige*; Minemura, Toshiyuki*; Tokai, Daisuke*; et al.

Fusion Engineering and Design, 88(9-10), p.2520 - 2524, 2013/10

 Times Cited Count:10 Percentile:61.16(Nuclear Science & Technology)

ITER TFC structures are large welding structures made of heavy thick stainless steels. JAEA plans to apply narrow gap TIG welding with FMYJJ1 which is full austenitic stainless filler material to manufacture TFC structure. FMYJJ1 is specified in "Codes for Fusion Facilities -Rules on Superconducting Magnet Structure (2008)". In order to evaluate effect of base material combinations and thickness of welded joint on tensile properties at 4 K, tensile tests were conducted at 4 K by using tensile specimens taken from 40 mm thickness weld joints of four combinations and 200 mm thickness ones of two combinations of base materials. These weld joints were manufactured by one side narrow gap TIG welding with FMYJJ1. As the results, it was confirmed that yield and tensile strengths of welded joint at 4K were decreased with decreasing of nitrogen of base material, and there were no large distribution of strengths at 4 K along the thickness of welded joints of 200 mm thickness.

Journal Articles

Development of structures for ITER toroidal field coil in Japan

Iguchi, Masahide; Chida, Yutaka; Takano, Katsutoshi; Kawano, Katsumi; Saito, Toru; Nakajima, Hideo; Koizumi, Norikiyo; Minemura, Toshiyuki*; Ogata, Hiroshige*; Ogawa, Tsuyoshi*; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4203305_1 - 4203305_5, 2012/06

 Times Cited Count:9 Percentile:47.58(Engineering, Electrical & Electronic)

Japan Atomic Energy Agency (JAEA) has responsibility to procure 19 structures for ITER toroidal field (TF) coils as in-kind components. JAEA plans to use materials specified in the material section of "Codes for Fusion Facilities; Rules on Superconducting Magnet Structure (2008)" issued by the Japan Society of Mechanical Engineers (JSME) in 2008. Large forged products were produced and their mechanical properties at 4K were evaluated. In addition, the following activities have been performed; (1) to optimize the design of each weld type identified in the manufacturing sequence, (2) to qualify typical welding procedure including repair, (3) to establish welding techniques other than narrow gap TIG welding with FMYJJ1, (4) to demonstrate the manufacturing procedures through manufacture of 1-m mockups and full-scale segments of TFC structure. This paper describes the results of material qualification and industrialization activities of manufacturing processes of ITER TFC structure.

Journal Articles

Development in fabrication structures for the ITER toroidal field coils

Iguchi, Masahide; Chida, Yutaka; Nakajima, Hideo; Ogawa, Tsuyoshi*; Katayama, Yoshinori*; Ogata, Hiroshige*; Minemura, Toshiyuki*; Miyabe, Keisuke*; Tokai, Daisuke*; Niimi, Kenichiro*

Teion Kogaku, 47(3), p.193 - 199, 2012/03

Japan Atomic Energy Agency (JAEA) has conducted qualification and rationalization activities in Japan in order to rationalize manufacturing procedure of ITER Toroidal Field (TF) coil structures. The activities included qualification of structural materials and qualification of welding procedure according to Japan Society of Mechanical Engineers (JSME) code constituted for fusion devices, demonstration of the manufacturing method and procedures through full-scale segments of TF coil structure. From results of these activities, JAEA confirmed applicability of JSME code to actual series TF coil structures as quality control method hence the quality of structural materials and weld joints of Gas Tungsten Arc Welding (GTAW) were satisfied ITER requirement. In addition, JAEA obtained knowledge of welding deformation of actual TF coil structures. This paper describes results of these qualification and development activities for TF coil structure.

Journal Articles

Validation of welding technology for ITER TF coil structures

Chida, Yutaka; Iguchi, Masahide; Takano, Katsutoshi; Nakajima, Hideo; Osemochi, Koichi*; Niimi, Kenichiro*; Tokai, Daisuke*; Gallix, R.*

Fusion Engineering and Design, 86(12), p.2900 - 2903, 2011/12

 Times Cited Count:10 Percentile:60.88(Nuclear Science & Technology)

TF coil structures, which support large electromagnetic force generated in TF coils under the cryogenic temperature (about 4K), are the mega welding structures composed of coil case and support structures made of high strength and high toughness stainless steel. JAEA started the study on welding trials for heavy thickness materials since 2008 and is planning of full scale mock-up model fabrication for main sub-components (1 set of inboard side and 1set of outboard side) in 2010 in order to investigate the technical issues for manufacturing of TF coil structures. This paper introduces the results on welding trials and status of full scale mock-up model fabrication to confirm the validity of welding technology and manufacturing design before fabricating actual products.

Journal Articles

Validation of fablicability for ITER TF coil structures

Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo; Osemochi, Koichi*; Niimi, Kenichiro*; Tokai, Daisuke*

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 5 Pages, 2011/07

The Japan Atomic Energy Agency (JAEA), acting as the Japan Domestic Energy Agency (JADA) in the ITER project, is responsible for the procurement of structures for 19 TF coils (including one spare). TF coil structures, which support large electromagnetic force generated in TF coils under the cryogenic temperature (about 4K), are the mega welding structures composed of coil case and support structures made of high strength and high toughness stainless steel. JAEA started the study on welding trials for heavy thickness materials since 2008 and is demonstrating of full scale mock-up model fabrication for main sub-components in 2010 in order to investigate the technical issues for manufacturing of TF coil structures. This paper introduces the results on welding trials and status of full scale mock-up model fabrication to confirm the validity of welding technology and manufacturing design before fabricating actual products. Enough weld joint performance was obtained with the base metal of JJ1 (high strength and high toughness stainless steel developed in Japan) and SS316LN, and also their combination using JJ1 filler wire (developed in Japan) by narrow gap GTAW process. Welding deformation such as angular distortion between outer plate and side plate of U-shape segment could be controlled and minimized by using effective restraint jig and no defects was observed in the welds by radiographic testing (RT) in trial manufacturing of 1m length. Validity of welding technology and manufacturing design such as fabrication sequence, welding procedure specification (WPS), quality control plan is confirmed during full scale mock-up model fabrication.

Journal Articles

JSME construction standard for superconducting magnet of fusion facility "Fabrication, installation, NDE and testing"

Nakahira, Masataka*; Niimi, Kenichiro; Irie, Hirosada*

Proceedings of 2009 ASME Pressure Vessels and Piping Division Conference (PVP 2009) (CD-ROM), 7 Pages, 2009/07

A standard of fabrication, installation, NDE and testing for superconducting magnets for fusion facility was developed. For construction of TF coil, a "Fabrication and Installation" standard FM-4000, accompanying a mandatory Appendix 41 "Welded Joint" and a "Nondestructive Examination" standard FM-5000 accompanying a mandatory Appendix 51 for "Ultrasonic Examination Method" and a "Pressure and Leak Testing" standard FM-6000 have been developed, based on other JSME standards for nuclear power plant (JSME S NB1) and also ASME Sec.III ND, NF or Sec.VIII-div.2 Since TF coil structure does not include radioactive materials but is operated under high stress produced by high magnetic field, it is not safety-relevant-barrier. The requirements to construction should be relaxed comparer with a fission reactor.

Oral presentation

Development of welding procedure for ITER-TF coil structure

Niimi, Kenichiro; Nakajima, Hideo; Hamada, Kazuya; Takano, Katsutoshi; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Chida, Yutaka*; Seto, Masaru*; Soejima, Koji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Structural code for manufacturing of structures for ITER TF coils

Nakajima, Hideo; Niimi, Kenichiro; Omori, Junji; Takano, Katsutoshi; Kawano, Katsumi; Tsutsumi, Fumiaki; Hamada, Kazuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Detailed manufacturing design and large-scale trial manufactures of ITER TF coil structures

Nakajima, Hideo; Niimi, Kenichiro; Omori, Junji; Takano, Katsutoshi; Hamada, Kazuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Validation of welding technology for ITER TF coil structures

Nakajima, Hideo; Chida, Yutaka; Takano, Katsutoshi; Tsutsumi, Fumiaki; Okuno, Kiyoshi; Niimi, Kenichiro*; Senda, Ikuo*

no journal, , 

no abstracts in English

Oral presentation

Validation of welding technology for ITER TF coil structures (Preliminary welding test)

Chida, Yutaka; Takano, Katsutoshi; Nakajima, Hideo; Osemochi, Koichi*; Niimi, Kenichiro*; Tokai, Daisuke*

no journal, , 

no abstracts in English

Oral presentation

Progress of procurement of TF coil structures

Iguchi, Masahide; Hemmi, Tsutomu; Chida, Yutaka*; Morimoto, Masaaki; Hong, Y.-S.*; Nishi, Hiroshi; Koizumi, Norikiyo; Tokai, Daisuke*; Niimi, Kenichiro*; Yamada, Hirokazu*

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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