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Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Development of instrumentation and control systems for the ITER diagnostic systems in JADA

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.

Journal Articles

Design study of a wide-angle infrared thermography and visible observation diagnostic on JT-60SA

Kamiya, Kensaku; Itami, Kiyoshi; Takeuchi, Masaki; Enokuchi, Akito*

Fusion Engineering and Design, 89(12), p.3089 - 3094, 2014/12

 Times Cited Count:4 Percentile:30.92(Nuclear Science & Technology)

Design study of a wide-angle infrared (IR) thermography and visible observation diagnostics for JT-60SA are reported. In order to image a large section inside the vacuum vessel (both in poloidal and toroidal directions), the optical system of endoscope is to provide a wide-angle view in the IR and visible range, which is being designed with a field of view of 106 degrees vertical and 63 degrees horizontal. The estimated spatial resolution is better than a few cm at a distance of 7.6 m from the front optics with a slit diameter of 4 mm.

Journal Articles

Development of the supervisory systems for the ITER diagnostic systems in JADA

Yamamoto, Tsuyoshi; Hashimoto, Yasunori*; Serizawa, Yasunori*; Inamoto, Shuji*; Sato, Kazuyoshi; Sugie, Tatsuo; Takeuchi, Masaki; Kawano, Yasunori

Fusion Engineering and Design, 89(5), p.532 - 535, 2014/05

 Times Cited Count:1 Percentile:8.88(Nuclear Science & Technology)

The diagnostic systems are essential for the plasma control and physics understandings. JAEA has proposed the new concept of supervisory system which manages operation sequences, current state and configuration parameters for the measurement based on our experiences in operating plasma diagnostic systems. We designed the supervisory system satisfying the requirements from both CODAC system and diagnostic systems. In our design, the tool which converts operational steps described as flowcharts into EPICS Records templates is introduced. This tool will ensure reduction of the system designers' efforts. We also designed the sequencing simulator that can submit transition commands internally instead of CODAC system for the calibration and commissioning. The mechanism which changes the limit values and consistency check algorithms in accordance with the conditions of the diagnostics system is also proposed.

Journal Articles

Development of divertor IR thermography for ITER

Takeuchi, Masaki; Sugie, Tatsuo; Ogawa, Hiroaki; Ishikawa, Masao; Shimada, Takahiko; Kusama, Yoshinori

Plasma and Fusion Research (Internet), 8(Sp.1), p.2402147_1 - 2402147_5, 2013/11

Divertor IR Thermography is one of the diagnostics which Japan is in charge of development in ITER project. The conceptual design has been performed so far, and the progress is reported here. By reducing the size of mirrors, and making the optical path a labyrinthine structure, the design of a new optics that fills requirements of both spatial resolution and neutron shielding has been advanced. To achieve the required measurement accuracy, the detected signal and the noises such as bremsstrahlung light, detector noise and thermal noise of optical components were evaluated. Higher photons than the bremsstrahlung light are obtained, excluding the low temperature range. The simulation calculation of reflection from wall was started. Detailed method of data processing of deriving the profiles of surface temperature in the divertor plates from the observed signals and in-situ calibration strategies of the optical system are important issues and will be discussed.

JAEA Reports

Maintenance of the cooling tower of the JRR-3's secondary cooling system

Fukushima, Manabu; Owada, Minoru; Ota, Kazunori; Takeuchi, Masaki; Goto, Shingo; Imahashi, Masaki; Terakado, Yoshibumi

JAEA-Technology 2010-028, 24 Pages, 2010/09

JAEA-Technology-2010-028.pdf:1.01MB

The cooling tower of the JRR-3's secondary cooling system is used to emit the heat from the core into the atmosphere. The appropriate maintenance of the cooling tower has helped the safe and stable reactor operation. Temperature of the secondary coolant had controlled constantly by changing the number of cooling fans. But, just after the number of fans changed, the temperature changed transiently and consequently the reactor thermal power changed. In order to amend this some weakness, the control system has improved to change the speed of fans constantly. The maintenance and improvement activities with the records of inspection are compiled to be utilized for future work.

JAEA Reports

Improvement of efficiency on ball-cleaning method for JRR-3 heat exchanger

Ota, Kazunori; Ikekame, Yoshinori; Owada, Minoru; Fukushima, Manabu; Oba, Toshinobu; Takeuchi, Masaki; Imahashi, Masaki; Murayama, Yoji

JAEA-Technology 2008-023, 31 Pages, 2008/03

JAEA-Technology-2008-023.pdf:3.3MB

JRR-3 uses shell and tube heat exchangers. The secondary coolant flushes into the tubes and the primary coolant flows outside of the tubes. The heat exchangers are cleaned with the ball-cleaning method, which is a method to clean inside of the tubes by passing the sponge balls with secondary coolant. Decline in the performance of heat exchanger could rise temperature of the primary coolant and then influence the safe and stable reactor operation. The effective way of ball-cleaning for JRR-3 heat exchangers is examined based on past cleaning data. The results show the optimal ball size and the way to determine the cleaning time.

JAEA Reports

None

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

PNC TN9410 87-202, 424 Pages, 1987/07

PNC-TN9410-87-202.pdf:79.52MB

None

Oral presentation

Observation of kinetic effect on Alfv$'e$n eigenmode damping

Matsunaga, Go; Toi, Kazuo*; Ikeda, Ryosuke*; Takeuchi, Masaki*; Takechi, Manabu; Nakajima, Noriyoshi*; Fukuyama, Atsushi*

no journal, , 

no abstracts in English

Oral presentation

Partial improvement of helium compressor V-ring device in JRR-3

Ishizaki, Katsuhiko; Ota, Kazunori; Takeuchi, Masaki; Imahashi, Masaki; Fukushima, Manabu

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan, 1

Kusama, Yoshinori; Ishikawa, Masao; Kondoh, Takashi; Ogawa, Hiroaki; Iwamae, Atsushi; Sugie, Tatsuo; Takeuchi, Masaki

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan

Kusama, Yoshinori; Kondoh, Takashi; Ishikawa, Masao; Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; Ono, Takehiro; Kawano, Yasunori; Imazawa, Ryota; Ogawa, Hiroaki; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of impurity influx monitor (divertor) for ITER

Ogawa, Hiroaki; Iwamae, Atsushi; Sugie, Tatsuo; Takeuchi, Masaki; Kusama, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan

Kawano, Yasunori; Kondoh, Takashi; Ishikawa, Masao; Hatae, Takaki; Yatsuka, Eiichi; Imazawa, Ryota; Ogawa, Hiroaki; Sugie, Tatsuo; Takeuchi, Masaki; Sato, Kazuyoshi; et al.

no journal, , 

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.

Oral presentation

Design of IR thermography for divertor in ITER

Takeuchi, Masaki; Sugie, Tatsuo; Ogawa, Hiroaki; Kusama, Yoshinori

no journal, , 

The physical investigations and conceptual design of the IR thermography for divertor in ITER have started. For the temperature measurements of the divertor plates, this diagnostic has a two color (3 and 5 micrometer) system and a spectroscopic system which has the measurement performance with 30 wavelength points in 1-5 micrometer and 100 spatial points. For physics studies, the temperature measurement is required in a wide range of 200-3600 $$^{circ}$$C with different time resolution (2 ms, 0.02 ms), and precisive spatial resolution (3 mm). Using the two optical systems installed in the equatorial port, they observe the nearest inner divertor plate and 9.9 m away outer divertor plate. Physical investigations such as the effect of diffraction and the emission intensity has been performed. To meet the spatial resolution, the aperture diameters of d $$>$$ 20 mm, d $$>$$ 10 mm are needed for the measurements of outer and inner divertor, respectively.

Oral presentation

Progress of impurity influx monitor (divertor) for ITER

Ogawa, Hiroaki; Iwamae, Atsushi; Sugie, Tatsuo; Takeuchi, Masaki; Kusama, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan

Kawano, Yasunori; Hatae, Takaki; Yatsuka, Eiichi; Sugie, Tatsuo; Takeuchi, Masaki; Ogawa, Hiroaki; Imazawa, Ryota; Ono, Takehiro; Kondoh, Takashi; Ishikawa, Masao; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of divertor impurity monitor and divertor IR thermography for ITER and estimation of the effect of reflection by first wall

Takeuchi, Masaki; Sugie, Tatsuo; Ogawa, Hiroaki; Kusama, Yoshinori; Ebisawa, Katsuyuki*; Wakabayashi, Kunio*; Nariai, Kyoji*; Tanimoto, Aki*; Kiyohara, Motosuke*

no journal, , 

no abstracts in English

Oral presentation

Development of divertor IR thermography for ITER

Takeuchi, Masaki; Sugie, Tatsuo; Ogawa, Hiroaki; Ishikawa, Masao; Shimada, Takahiko; Kusama, Yoshinori

no journal, , 

In ITER project, it reports on the progress of the conceptual design of Divertor IR Thermography which is one of the diagnostics Japan is in charge of development. The conceptual design of the optical system was done based on the measurement requirement, and the performance was evaluated. The angle of field of view is 2.5 degree for the outer divertor and 4.0 degree for the inner divertor, therefore wide fields of view are achieved. The spatial resolution fills 3 mm of the measurement requirement in the center field of view though it depends on the observed wavelength. Moreover, nuclear heating of mirrors in the optical system is 0.1 W / cc excluding the first mirror. The prospect that the mirrors can be cooled is obtained. Future tasks include optimization of the optical system that spatial resolution coexists with neutron shielding, development of calibration method and the mechanical designs of shutters and mirror holders.

Oral presentation

Recent design of impurity influx monitor (divertor) for ITER

Ogawa, Hiroaki; Sugie, Tatsuo; Takeuchi, Masaki; Kusama, Yoshinori

no journal, , 

no abstracts in English

41 (Records 1-20 displayed on this page)