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Journal Articles

Development of Decommissioning Engineering Support System (DEXUS) of the Fugen NPS

Iguchi, Yukihiro; Sekiguchi, Mineo; Kanehira, Yoshiki

Journal of Nuclear Science and Technology, 41(3), p.367 - 375, 2004/03

 Times Cited Count:39 Percentile:90.66(Nuclear Science & Technology)

The Fugen Nuclear Power Station has shut down permanently in March 2003, and preparatory activities are underway to decommission Fugen NPS. An engineering system to support the decommissioning is being developed to create a dismantling plan.

JAEA Reports

None

Kitabata, Takuya; Shimono, Kimihiro; sekiguchi, mineo; Matsushima, Akira

JNC TN4410 2003-004, 42 Pages, 2003/03

JNC-TN4410-2003-004.pdf:11.33MB

None

JAEA Reports

Survey and study on examination equipments for in-vessel components inspection in JOYO(II)

*; Sekiguchi, Mineo*; *; *; *

PNC TJ9164 95-012, 50 Pages, 1995/03

PNC-TJ9164-95-012.pdf:1.64MB

As a part of the development of the in-service inspection and repair(ISI & R) technology of FBR, study on examination equipments as visual method to verify in-vessel structures and assemblies was conducted. The objects of the study were higher resolution equipments using ultrasonic transducer technology to examine top area of assemblies in core support structure and parts of the core support structure where entrance nozzles of assemblies were inserted and withdrawn when refueling in 'JOYO'. As the result of the study, basic specification and structures of transducers and signal processing units, and conceptual design of basic structure of drive mechanics for the transducers were derived. The items and plan of the development of the equipments were made.

JAEA Reports

Evaluation of the automatic reactor operation system for JOYO

Sato, Masuo*; Fukawa, Naohiro*; Tamaoki, Tetsuo*; Iwashita, Tsuyoshi*; Ito, Atsushi*; Sekiguchi, Mineo*; Yamanaka, Toshikatsu*; Yoshida, Megumi*; Maruyama, Fumi*; Yamamoto, Kazuhiko*

PNC TJ9164 88-007, 96 Pages, 1988/11

PNC-TJ9164-88-007.pdf:2.11MB

The automatic reactor operation syste for JOYO is evaluated. In JOYO, by realizing the automatic operation of control rod, the reduction of the operator's load will be performed, and by improving the man-machine interface, the operability will be also improved, Still, in order to improve the reliability and safety of operator, following items are evaluated. In these evaluations, two kinds of automatic reactor operation systems are considered, one is limited to a control rod operation and the other is to an overall plant operation with steam generators. (1)Configuration of the automatic control rod operation system and the automatic plant operation system. (2)Control algorithm by using the knowledge engineering. (3)Methods of the man-machine interface and the operation against emergency conditions. (4)Scope of modification of the present control rod drive system and central control panels. And, the problems which are necessary to be solved to implement this system, are evaluated. Basic configuration of the automatic control rods operation system and the automatic plant operation system are established, and it is ascertained that the present control rod drive system will be useful to the control rod position control to realize the automatic control rod operation without any modification of the control rod drive mechanism.

JAEA Reports

The Operational and maintenance experience of the fuel handling facility of "JOYO" (5)

Sekiguchi, Mineo*; *; *; *; *; *; *

PNC TN9410 87-124, 392 Pages, 1987/09

PNC-TN9410-87-124.pdf:11.38MB

The fuel handling facility was set up in oct. 1974. The operational tests were done in three phases successively, first in air, then in argone gas and finally under sodium at 250$$^{circ}$$C. Initial fuel loading for criticality of "Joyo" started in March 1977 and the criticality was achieved in April. After this, lower power test, power up test for 50 MW, 50 MW cycle operations, power up test for 75 MW, and 75 MW cycle operations followed till Dec. 1981. After the core conversion from the Breeding Core (MK-I Core) to the Irradiation Core (MK-II Core), 100 MW power achieved in March 1983 and the 100 MW cycle operation is going well now. In the meanwhile, the fuel handling facility transfered about 600 core assemblies and were checked five times as the regular inspection. This report reviews the experiences of operation and maintenance of the fuel handling facility from Jan. 1983 to Dec. 1985.

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