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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

Coulomb excitation of $$^{174}$$Hf K-isomer; $$gamma$$-ray spectroscopy with high-spin isomer beam

Morikawa, Tsuneyasu*; *; Morita, Kosuke*; *; Murakami, Takeshi*; *; *; G.H.Liu*; A.Ferragut*; *; et al.

Physics Letters B, 350, p.169 - 172, 1995/00

 Times Cited Count:19 Percentile:71.02(Astronomy & Astrophysics)

no abstracts in English

Journal Articles

A Model to predict the ultimate failure of coated fuel particles during core heatup events

Ogawa, Toru; Minato, Kazuo; Fukuda, Kosaku; ; ; Sekino, Hajime; ; Ito, Tadaharu; ;

Nuclear Technology, 96, p.314 - 322, 1991/12

 Times Cited Count:12 Percentile:76.66(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment Run SB-HL-04

Kukita, Yutaka; Nakamura, Hideo; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yonomoto, Taisuke; et al.

JAERI-M 91-040, 122 Pages, 1991/03

JAERI-M-91-040.pdf:3.42MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment; Run SB-HL-02

Kukita, Yutaka; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; et al.

JAERI-M 90-039, 122 Pages, 1990/03

JAERI-M-90-039.pdf:3.38MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV/LSTF 5% hot leg break experiment Run SB-HL-01

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-225, 117 Pages, 1990/01

JAERI-M-89-225.pdf:3.53MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 5% cold leg break LOCA experiment Run SB-CL-08

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-220, 127 Pages, 1990/01

JAERI-M-89-220.pdf:3.57MB

no abstracts in English

JAEA Reports

Irradiation Experiments of Coted Particle Fuels by Gas-Swept Capsules,(II); Irradiation by 75F4A and 75F5A Capsules

; ; ; Tobita, Tsutomu; Minato, Kazuo; Yamamoto, Katsumune; ;

JAERI-M 87-020, 79 Pages, 1987/02

JAERI-M-87-020.pdf:4.96MB

no abstracts in English

JAEA Reports

Irradiation Experiment of Coated Particle Fuels by Sweep Gas Capsule(Irradiation by 74F-9J Capsule)

; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune; ;

JAERI-M 84-054, 65 Pages, 1984/03

JAERI-M-84-054.pdf:2.84MB

no abstracts in English

Journal Articles

3.1.1.Closed devices 1)Low $$beta$$ types i)Tokamak

; *; *; *; *; *; *

Nihon Butsuri Gakkai-Shi, 30(11), p.810 - 840, 1975/11

no abstracts in English

Oral presentation

Basic test for making Waste package for Spent resin disposal

Otani, Hiroshi; Higashiura, Norikazu; Mizui, Hiroyuki; Endo, Nobuyuki*; Katagiri, Genichi*; Oshio, Tadashi*; Ogawa, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Basic test for making waste package for spent resin disposal, 1; Volume reduction and stabilization process by low pressure oxygen plasma process for spent resin

Mizui, Hiroyuki; Otani, Hiroshi; Higashiura, Norikazu; Onozaki, Kimihiro*; Katagiri, Genichi*; Endo, Nobuyuki*; Ogawa, Hideo*; Kaneda, Yoshihisa*

no journal, , 

The applicable prospect for spent resin disposal including inhibitor was acquired by basic test of using low pressure oxygen plasma method.

Oral presentation

Study on radioactive substance osmosis for basis concrete of equipment

Mizui, Hiroyuki; Ito, Hideki*; Kume, Kyo*; Ogawa, Hideo*; Kaneda, Yoshihisa*

no journal, , 

Radioactive substance osmosis for basis concrete of equipment was estimated, to treat and dispose in decommissioning project of Fugen Decommissioning Engineering Center (Fugen). In this study, the osmosis of Cobalt (non-radioactive) in liquid to concrete was observed by using PIXE method and others. And, the crack depth was measured by using UT method and others. As a result, it was confirmed that radioactive substance was osmosed to depth of crack, if Cobalt in liquid was touched with the crack of concrete, but the hydrophobic coatings of surface protect the liquid osmosis in short time. And, the relationship between crack depth and liquid osmosis was observed as nearly correlation. The continuous study at Fugen will establish the estimation method for area of osmosis contamination possibilities for basis concrete of equipment in the near future.

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