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Kobayashi, Jun; Ezure, Toshiki; Tanaka, Masaaki; Kamide, Hideki
Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 5 Pages, 2016/11
JAEA has been conducting a design study for an advanced large-scale sodium-cooled fast reactor (SFR). Hot sodium from the fuel subassembly can mix with the cold sodium from the control rod (CR) channel at the bottom of Upper Internal Structure (UIS). Temperature fluctuation due to the fluid mixing at the core outlet may cause high cycle thermal fatigue at the bottom of UIS. JAEA had performed a water experiment to examine countermeasures for the significant temperature fluctuation generated at the bottom of SFRs UIS. Meanwhile, a self-actuated shutdown system (SASS) is equipped in a backup control rod (BCR) channel to ensure reactor shutdown. The BCR guide tubes have a flow guide structure "flow-collector" to provide reliable operation of SASS. Flow-collector may affect the thermal mixing behavior at the bottom of the UIS. This study has investigated the influence of the flow- collector on characteristics of the temperature fluctuation around the BCR channels.
Kobayashi, Jun; Ezure, Toshiki; Kamide, Hideki; Oyama, Kazuhiro*; Watanabe, Osamu*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05
A column type upper internal structure (UIS) is installed in the upper plenum of reactor vessel in JSFR. High cycle thermal fatigue may occur at the bottom plate (CIP) of the UIS where the hot sodium from the fuel subassembly can mix with the cold sodium from the control rod channel and the blanket fuel subassembly. We have been conducted a water experiment using a reactor upper plenum model to grasp the thermal-hydraulic phenomena around control rod (CR) channels, and to obtain countermeasures for significant temperature fluctuation on the CIP. The experimental apparatus has 1/3 scale and 60
sector model of the reactor upper plenum. By the experiment, characteristics of fluid temperature fluctuation between the handling head of the assemblies and the CIP are measured and countermeasure for the significant temperature fluctuation generation will be discussed on the influence of the distance from the handling head outlet to the lower surface of the CIP.
Sato, Minoru; Tsugita, Tomonori; Oshima, Takayuki; Sakata, Shinya; Iwasaki, Keita*; Matsuda, Toshiaki; Iba, Katsuyuki; Ozeki, Takahisa
Fusion Engineering and Design, 71(1-4), p.145 - 149, 2004/06
Times Cited Count：7 Percentile：44.60(Nuclear Science & Technology)Data processing system in JT-60 has been used CAMAC widely for control and data acquisition of plasma diagnostic. However, it has passed over fifteen years from the operation, and the problem is caused for maintenance and function enhancement by the deterioration. Then, Mini-computer and microcomputer ,which control the CAMAC system were replaced workstation based on UNIX-OS, and these system were remodeled by developing the application software for screen control by GUI and for constructing environment of remote diagnostic through the network. In addition, CAMAC device driver for Linux has been developed in for next CAMAC control system.
Yonekawa, Izuru
Fusion Engineering and Design, 43(3-4), p.321 - 325, 1999/00
Times Cited Count：11 Percentile：63.06(Nuclear Science & Technology)no abstracts in English
Oka, Kiyoshi; Kakudate, Satoshi; ; ; ; Tada, Eisuke; ; Shibanuma, Kiyoshi
Fusion Technology 1998, 2, p.1701 - 1704, 1998/00
no abstracts in English
Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; ;
J. Robot. Mechatron., 10(2), p.139 - 145, 1998/00
no abstracts in English
Totsuka, Toshiyuki
JAERI-M 93-158, 36 Pages, 1993/08
no abstracts in English
Niitsuma, Yasushi; Murao, Yoshio
JAERI-M 91-213, 73 Pages, 1992/01
no abstracts in English
; ; Itabashi, Keizo; Yonezawa, Minoru
1st Pacific Conf.on New Information Technology, p.195 - 203, 1987/00
no abstracts in English
; ; ; ; ; Hanashima, Susumu;
JAERI-M 85-198, 60 Pages, 1985/12
no abstracts in English
;
JAERI-M 9695, 87 Pages, 1981/09
no abstracts in English
JAERI-M 9283, 87 Pages, 1981/02
no abstracts in English
; Murao, Yoshio;
JAERI-M 8165, 31 Pages, 1979/03
no abstracts in English
Journal of Applied Physics, 47(5), p.2241 - 2242, 1976/05
Times Cited Count：1no abstracts in English
Kobayashi, Jun; Kimura, Nobuyuki*; Tanaka, Masaaki; Kamide, Hideki; Oyama, Kazuhiro*; Watanabe, Osamu*
no journal, ,
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
no journal, ,
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.
Tomita, Yutaka; Kumata, Masahiro; Wakabayashi, Shuji; Kijima, Yuichi; Yamamoto, Yoichi; Oda, Tetsuzo
no journal, ,
Kobayashi, Jun; Ezure, Toshiki; Tanaka, Masaaki; Kamide, Hideki
no journal, ,
no abstracts in English
Kobayashi, Jun; Ezure, Toshiki; Tanaka, Masaaki; Kamide, Hideki
no journal, ,
JAEA has been conducting a design study for an advanced large-scale sodium-cooled fast reactor (SFR). Hot sodium from the fuel subassembly can mix with the cold sodium from the control rod (CR) channel and blanket assemblies at the bottom of Upper Internal Structure (UIS). Temperature fluctuation due to the fluid mixing at the core outlet may cause high cycle thermal fatigue at the bottom of UIS. JAEA had performed a water experiment to examine countermeasures for the significant temperature fluctuation generated at the bottom of SFRs UIS. A water experiment was conducted using a 1/3 scale 60-sector model of the reactor core and upper plenum. The temperature fluctuations near the cold fluid outlets were determined, and several countermeasures were tested. It was confirmed that these countermeasures could reduce the temperature fluctuations at the bottom of the UIS.
