Refine your search:     
Report No.
 - 
Search Results: Records 1-14 displayed on this page of 14
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of laser welding technology for fully austenite stainless steel

Takano, Katsutoshi; Koizumi, Norikiyo; Serizawa, Hisashi*; Tsubota, Shuho*; Makino, Yoshinobu*

Yosetsu Gakkai Rombunshu (Internet), 33(2), p.126 - 132, 2015/06

A radial plates (RP), which is used in Toroidal field (TF) coil in ITER, is significantly large, such as 13 m height and 9 m wide, but thin, such as 10 cm thick, and are made of full-austenite stainless steel. Even though they are very large structures, high manufacturing tolerances are required. In addition, it is required that each RP is fabricated every three weeks. Therefore, the authors develop efficient manufacturing methods of RP. The laser welding is selected as a welding method of RP. But the development of the high power laser welding technology is necessary to avoid hot cracking of the materials used for RP, namely full austenite stainless steel with high nitrogen content. The authors carried out trial aiming at an application of the laser welding to RP. As a result, it is effective to optimize the angle of inclination of the weld head. It also seems sensitivity of hot cracking can be less by optimizing the chemical composition of materials to use for RP. It was therefore demonstrated that the application of the laser welding technology in the full austenite stainless steel.

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.

Fusion Science and Technology, 66(1), p.46 - 56, 2014/07

 Times Cited Count:4 Percentile:29.67(Nuclear Science & Technology)

Journal Articles

IFMIF; Overview of the validation activities

Knaster, J.*; Arbeiter, F.*; Cara, P.*; Favuzza, P.*; Furukawa, Tomohiro; Groeschel, F.*; Heidinger, R.*; Ibarra, A.*; Matsumoto, Hiroshi*; Mosnier, A.*; et al.

Nuclear Fusion, 53(11), p.116001_1 - 116001_18, 2013/11

AA2013-0294.pdf:2.55MB

 Times Cited Count:65 Percentile:93.95(Physics, Fluids & Plasmas)

The IFMIF/EVEDA project under the Broader Approach Agreement between Japan and EU aims at allowing a rapid construction phase of IFMIF in due time. The three main facilities, (1) the Accelerator Facility, (2) the Target Facility and (3) the Test Facility, are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho. The world largest liquid Li test loop is running in Oarai with an ambitious experimental programme for the years ahead. A full scale high flux test module that will house $$sim$$ 1000 small specimens developed jointly in Europe and Japan has been constructed in Germany together with its He gas loop. A full scale medium flux test module to carry out on-line creep measurement has been constructed in Switzerland.

Journal Articles

Development of lithium target system in engineering validation and engineering design activity of the International Fusion Materials Irradiation Facility (IFMIF/EVEDA)

Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Fukada, Satoshi*; Yagi, Juro*; Ida, Mizuho; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 88(12), p.691 - 705, 2012/12

AA2012-1008.pdf:2.42MB

no abstracts in English

Journal Articles

Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER

Hirose, Takanori; Seki, Yohji; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Tsuru, Daigo; Enoeda, Mikio; Serizawa, Hisashi*; Yamaoka, Hiroto*

Fusion Engineering and Design, 85(7-9), p.1426 - 1429, 2010/12

 Times Cited Count:8 Percentile:48.56(Nuclear Science & Technology)

This paper describes packing experiment of tritium breeder pebbles into a full-scale Tritium-Breeder-Container (TBC) mockup. A full scale mockup of the TBC for Water Cooled Solid Breeder - Test Blanket Module has been successfully developed using a reduced activation ferritic steel, F82H. A full-scale TBC mock-up was successfully fabricated with the fiber laser welding, and its dimensions are 74 $$times$$ 112 $$times$$ 990 mm$$^{3}$$. It was confirmed to be gastight under pressurized helium up to 0.5 MPa. By using the fabricated mockup, packing tests were performed with Li$$_{2}$$TiO$${3}$$ pebbles of 1mm diameter. The pebbles were packed into the TBC through sweep gas lines penetrating the tube plates. X-ray tomography revealed that dense packing was uniformly achieved in the whole TBC.

Journal Articles

Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

Tanigawa, Hiroyasu; Hirose, Takanori; Shiba, Kiyoyuki; Kasada, Ryuta*; Wakai, Eiichi; Serizawa, Hisashi*; Kawahito, Yosuke*; Jitsukawa, Shiro; Kimura, Akihiko*; Kono, Yutaka*; et al.

Fusion Engineering and Design, 83(10-12), p.1471 - 1476, 2008/12

 Times Cited Count:78 Percentile:97.58(Nuclear Science & Technology)

Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. F82H, which were developed and studied in Japan, was designed with an emphasis on high temperature properties and weldability. The database on F82H properties is currently the most extensive available among the existing RAFMs. The objective of this paper is to review the R&D status of F82H and to identify the key technical issues for the fabrication of an ITER Test Blanket Module (TBM) suggested by recent achievements in Japan.

Oral presentation

Optimization of electron beam welding conditions for fabrication of DEMO blanket box structure

Hirose, Takanori; Shirai, Yuma*; Ogiwara, Hiroyuki*; Mori, Hiroaki*; Serizawa, Hisashi*; Saida, Kazuyuki*; Nishimoto, Kazutoshi*; Tanigawa, Hiroyasu

no journal, , 

no abstracts in English

Oral presentation

Present status of R&D on breeding functional components in ITER-TBM, 1; Mock-up fabrication of tritium breeding layer for solid breeding ITER-TBM

Hirose, Takanori; Tanigawa, Hiroyasu; Enoeda, Mikio; Kawahito, Yosuke*; Serizawa, Hisashi*; Katayama, Seiji*

no journal, , 

no abstracts in English

Oral presentation

R&D of lithium target and test facilities for the fusion neutron source

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Kikuchi, Takayuki; Ito, Yuzuru*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Charpy impact properties of F82H/316L and 316L/316L welded steels

Nakaniwa, Koichi; Ito, Yuzuru; Furuya, Kazuyuki*; Serizawa, Hisashi*; Kawahito, Yosuke*; Wakai, Eiichi

no journal, , 

no abstracts in English

Oral presentation

Progress and scheme of IFMIF/EVEDA project; Lithium target facility

Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.

no journal, , 

Oral presentation

Status of lithium target facility development in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakaniwa, Koichi; Ito, Yuzuru; Tanaka, Hiroshi; Tsuji, Yoshiyuki*; Ito, Takahiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Technical issues of welding of reduced activation ferritic/martensitic steels at the fabrication of ITER test blanket module

Tanigawa, Hiroyasu; Ogiwara, Hiroyuki; Hirose, Takanori; Shiba, Kiyoyuki; Serizawa, Hisashi*; Kawahito, Yosuke*; Tanaka, Manabu*; Katayama, Seiji*; Mori, Hiroaki*; Nishimoto, Kazutoshi*

no journal, , 

Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. These steels have been developed based on substantial industrial experience with high chromium heat resistant ferritic/martensitic steels (such as modified 9Cr-1Mo), but with Mo and Nb replaced by W and Ta, respectively. The objective of this paper is to review the R&D status of F82H and to identify the key technical issues for the fabrication of an ITER Test Blanket Module (TBM) suggested by recent achievements in Japan.

Oral presentation

Characterization of NITE-SiC/SiC composites by acoustic emission

Nozawa, Takashi; Serizawa, Hisashi*; Koyama, Akira*; Tanigawa, Hiroyasu

no journal, , 

Of many characterization methods, the acoustic emission (AE) technique is one of effective tools to monitor crack behavior in the material during the test and this technique has recently been applied to various composite materials. This study aims to apply the acoustic emission technique to the latest ceramic composite material: a nano-infiltration transient-eutectic phase sintered (NITE) silicon carbide fiber reinforced silicon carbide (SiC/SiC) composite to identify correlation between failure damage accumulation behavior and the AE signal pattern. Two types of fiber architecture: unidirectional (UD) and plain-weave (P/W) were accordingly addressed and tensile tests were conducted. Specifically, the Wavelet analysis was applied to evaluate the time-dependent damage accumulation process and to classify the key failure mechanism of this class of composites.

14 (Records 1-14 displayed on this page)
  • 1