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Yamamoto, Tsuyoshi; Hashimoto, Yasunori*; Kitazawa, Sin-iti; Yatsuka, Eiichi; Hatae, Takaki; Sugie, Tatsuo; Ogawa, Hiroaki; Takeuchi, Masaki; Kawano, Yasunori; Itami, Kiyoshi
Fusion Engineering and Design, 96-97, p.1012 - 1016, 2015/10
Times Cited Count：4 Percentile：33.25(Nuclear Science & Technology)Japan Domestic Agency (JADA) is responsible for six diagnostic systems in the ITER project. We have successfully developed an instrumentation and control (I&C) system for the diagnostic systems. The I&C system manages internal operations for measurement such as health checks of sensors, configuration of measurement parameters, and consistency checks between measurement parameters. We developed a conversion tool to convert operational flowcharts to EPICS records. The sequencing management function coordinates the execution of operation steps by monitoring changes in the record values. It was designed so that the relationship between the records and steps is determined automatically according to the flowcharts as much as possible. We validated the performance of the I&C system for the thermocouple measurement system, and are continuing the development of even more complex I&C systems for other JADA diagnostic systems.
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.
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.
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.
Shiihara, Katsunori*; Makino, Yoshinobu*; Ogawa, Tsuyoshi*; Asai, Satoru*; Kanahara, Toshio*; Senda, Ikuo*; Okuno, Kiyoshi; Koizumi, Norikiyo; Matsui, Kunihiro
Proceedings of 26th International Congress on Applications of Lasers & Electro-Optics (ICALEO 2007) (CD-ROM), p.316 - 324, 2007/10
The toroidal field coil is manufactured as one of superconducting coil systems in the ITER. For welding the cover plate of TF coil, the prevention of the thermal effect on the coil and the deformation of the whole coil are required. Moreover, the application of high efficient welding is required in consideration for the productivity. Therefore, laser-arc hybrid welding process was investigated for the application to the cover plate welding, because its process is superior in the tolerance of the joint gap and the ease of the control for the heat input. In the experiment, it was confirmed that the application of laser-arc hybrid welding with the double gas shielding for high concentration arc and the filler wire for controlling the deposit amount is effective in the joint gap up to 0.8mm. Besides, twin spot laser head with the arc was developed in order to weld the both sides of cover plate simultaneously. By the optimization of welding condition for twin spot laser-arc hybrid welding process, it was confirmed to be effective in the prevention of the gap movement during welding and the acquisition of the proper penetration without the weld defect. Finally, the effectiveness of laser-arc hybrid welding for the welding deformation and the weldability on the quality was verified by the scale model test with the actual shape.
Asai, Satoru*; Ogawa, Takeshi*; Makino, Yoshinobu*; Shiihara, Katsunori*; Senda, Ikuo*; Okuno, Kiyoshi; Koizumi, Norikiyo; Matsui, Kunihiro
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Ogawa, Tsuyoshi*; Asai, Satoru*; Makino, Yoshinobu*; Shiihara, Katsunori*; Senda, Ikuo*; Okuno, Kiyoshi; Koizumi, Norikiyo; Matsui, Kunihiro
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Asai, Satoru*; Ogawa, Tsuyoshi*; Makino, Yoshinobu*; Shiihara, Katsunori*; Senda, Ikuo*; Okuno, Kiyoshi; Koizumi, Norikiyo; Matsui, Kunihiro
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Kawano, Yasunori; Kondoh, Takashi; Ishikawa, Masao; Hatae, Takaki; Yatsuka, Eiichi; Imazawa, Ryota; Ogawa, Hiroaki; Sugie, Tatsuo; Takeuchi, Masaki; Sato, Kazuyoshi; et al.
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Recent progress in development of ITER diagnostic systems in Japan is presented as briefly shown below. (1) Microfission Chamber: A prototyping of vacuum feedthrough showed that the vacuum leak rate satisfies that of ITER requirement. (2) Thomson scattering (edge): A new method proposed for the measurement of anisotropic electron temperature was presented. (3) Poloidal Polarimeter: Measurement accuracy of the poloidal polarimeter was evaluated so that the accuracy of resultant current profile can satisfy the ITER measurement requirement. (4) Impurity influx monitor (divertor): By improvement of the design of equatorial port optics, expected detected light was 16 times increased in comparison with that of the previous design. (5) Divertor thermocouples (outer target): Investigation was started about the fixation method of the thermocouple on the side of divertor outer target. (6) Divertor IR thermography: Conceptual design activity was started for equatorial port optics.
Kawano, Yasunori; Hatae, Takaki; Yatsuka, Eiichi; Sugie, Tatsuo; Takeuchi, Masaki; Ogawa, Hiroaki; Imazawa, Ryota; Ono, Takehiro; Kondoh, Takashi; Ishikawa, Masao; et al.
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Arai, Yasuo; Nishi, Tsuyoshi; Ogawa, Shinta*
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A concept of sphere-pac type nitride fuel for ADS consisting of (Pu,MA)N and ZrN particles was proposed in order to mitigate the burden of dedicated MA-transmutation fuel cycle based on double-strata fuel cycle concept. Assuming several conditions, radial temperature distribution was compared between the sphere-pac and pellet type fuel elelments. Although the thermal conductivity of the sphere-pac particle bed is lower than that of the pellet, the maximum temperature of the sphere-pac type fuel can be lower than that of the pellet-type fuel thanks to small temperature rise in the gap region. It was suggested from the results that the concept of sphere-pac type nitride fuel is applicable when several elemental technologies for fuel fabrication, such as preparation of high dense particle and their close packing, are developed. The new concept can contribute to the mitigation of fuel cycle including fuel fabrication, reprocessing and waste management.
Itami, Kiyoshi; Kawano, Yasunori; Hatae, Takaki; Ishikawa, Masao; Ogawa, Hiroaki; Sugie, Tatsuo; Yamamoto, Tsuyoshi; Kondoh, Takashi; Kitazawa, Sin-iti; Yatsuka, Eiichi; et al.
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Yamamoto, Tsuyoshi; Kitazawa, Sin-iti; Yatsuka, Eiichi; Hatae, Takaki; Sugie, Tatsuo; Ogawa, Hiroaki; Takeuchi, Masaki; Kawano, Yasunori; Itami, Kiyoshi
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Japan Domestic Agency (JADA) will procure diagnostic systems in the ITER project. Japan Atomic Energy Agency (JAEA), as JADA, is developing the diagnostic systems. JAEA develops supervisory control system for diagnostics systems to conduct internal operation for measurements using EPICS (Experimental Physics and Industrial Control System), which is recommended to develop control systems by ITER Organization. We present design of the supervisory control system and development plan.
Kawano, Yasunori; Takeuchi, Masaki; Tojo, Hiroshi; Kitazawa, Sin-iti; Yamamoto, Tsuyoshi; Takeyama, Shigeharu; Yatsuka, Eiichi; Imazawa, Ryota; Sakuma, Takeshi; Shimada, Takahiko; et al.
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Kitazawa, Sin-iti; Ishikawa, Masao; Kawano, Yasunori; Imazawa, Ryota; Hatae, Takaki; Yatsuka, Eiichi; Sugie, Tatsuo; Takeuchi, Masaki; Ogawa, Hiroaki; Yamamoto, Tsuyoshi; et al.
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Yamamoto, Tsuyoshi; Hatae, Takaki; Yatsuka, Eiichi; Sugie, Tatsuo; Ogawa, Hiroaki; Takeuchi, Masaki; Kitazawa, Sin-iti; Ota, Kazuya*; Hashimoto, Yasunori*; Nakamura, Kitaru*; et al.
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no abstracts in English
Yamamoto, Tsuyoshi; Hatae, Takaki; Yatsuka, Eiichi; Takeuchi, Masaki; Ogawa, Hiroaki; Kitazawa, Sin-iti; Imazawa, Ryota; Ishikawa, Masao; Kawano, Yasunori; Itami, Kiyoshi
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Japan Atomic Energy Agency is developing control and data acquisition systems for poloidai polarimeter, edge Thomson scattering system, divertor impurity monitor, IR thermography and micro fission chamber in ITER project. We developed supervisory control system, which coordinates internal devices such as detectors and laser system following discharge sequence, leading other domestic agencies. Supervisory system configures measurement parameters and performs consistency check between the parameters. We also developed sequence control function to coordinate control programs for measurement and auxiliary devices complying to ITER standards and guidelines. A flowchart conversion tool was developed. The conversion tool reduced troubles in the program codes. It also makes changes of control logic flexible. We also developed prototype data acquisition system communicating with a central control simulator. The prototype demonstrates that our system design was valid.
Yamamoto, Tsuyoshi; Yatsuka, Eiichi; Hatae, Takaki; Ota, Kazuya*; Hashimoto, Yasunori*; Nakamura, Kitaru*; Sugie, Tatsuo*; Takeuchi, Masaki; Kitazawa, Sin-iti; Ogawa, Hiroaki; et al.
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ITER edge Thomson scattering system (ETS) is being developed in Japan. ETS measures electron density and temperature profiles using high energy laser more than 5 J. Therefore, ETS has to contain interlock system to protect optical components from damage caused by laser malfunctions. As same as interlock system, conventional control also should sustain components good conditions. We proposed new method that templates for program codes of conventional control were generated from interlock logics using information technologies such as semantic web technique. In addition, we applied the plant description data to risk analysis. HAZOP (hazard and operability study) is a useful method to indentify hazards and problems in a system. To describe plant functionalities and behaviors using ontology for functional knowledge, list of possible risks are extracted from the description by applying substitution and/or inference rules.
Itami, Kiyoshi; Kawano, Yasunori; Hatae, Takaki; Sugie, Tatsuo*; Ogawa, Hiroaki; Ishikawa, Masao; Kitazawa, Sin-iti; Imazawa, Ryota; Yatsuka, Eiichi; Yamamoto, Tsuyoshi; et al.
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no abstracts in English
