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JAEA Reports

Periodic Safety Review of the Experimental Fast Reactor JOYO; Review of Aging Management

Isozaki, Kazunori; Ogawa, Toru; Nishino, Kazunari; Kaito, Yasuaki; Ichige, Satoshi; Sumino, Kozo; Suto, Masayoshi; Kawahara, Hirotaka; Suzuki, Toshiaki; Takamatsu, Misao; et al.

JNC TN9440 2005-003, 708 Pages, 2005/05

JNC-TN9440-2005-003.pdf:31.46MB

Periodic safety review (Review of the aging management) which consisted of Technical review on aging for the safety related structures, systems and components and Establish a long term maintenance program was carried out up to April 2005.1. Technical review on aging for the safety related structures, systems and components It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them 2. Establish a long term maintenance program The long term maintenance program during JPY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection or renewal based on the long term maintenance program, in addition to the spontaneous inspection long-term schedule of the long term voluntary inspection plan, could prevent the loss of function of the safety related structures, systems and components in future.

JAEA Reports

Fuel Failure Simulation Test in JOYO; FFDL in-pile test(III)

Ito, Chikara; Ito, Hideaki; Ishida, Koichi; Hatoori, Kazuhiro; Oyama, Kazuhiro; Sukegawa, Kazuya*; Murakami, Takanori; Kaito, Yasuaki; Nishino, Kazunari; Aoyama, Takafumi; et al.

JNC TN9410 2005-003, 165 Pages, 2005/03

JNC-TN9410-2005-003.pdf:12.66MB

At experimental fast reactor JOYO, appraisal of detection efficiency of behavior and FFD and FFDL of the fission product which is discharged inside the furnace as one of safety research of the country, is carried out. In MK-II core, the slit in the gas plenum part of the test sub-assembly, the test which irradiates this(1985 April, FFDL in-pile test(I)), providing the slit in the fuel column part of the test sub-assembly, the test which it irradiates(1992 November, FFDL in-pile test(II)) were carried out.MK-III reactor core replacement was completed and started in 2004. That the behavior in the system of FP with the reactor core replacement and so on changes in the MK-III reactor core and to have an influence on the sensitivity and the replying of FFD and FFDL are thought of. Therefore, behavior of FP in the fuel failure in the MK-III reactor core, the performance of FFD and FFDL must be confirmed beforehand. Moreover, to prepare for the fuel failure and the RTCB test which is doing a future plan, and to confirm a plant operation procedure in the fuel failure in MK-III reactor core operation and to attempt for the correspondency to improve are important.Therefore, in the period from 2004 November 11th to November 29th, it carried out the FFDL in-pile(III). It did a series of plant operation to stop a nuclear reactor after loading a reactor core center with the fuel element for the test which provided an artificial slit for the fuel cladding in the MK-III reactor core and irradiating it and detecting fuel damaging and to take out fuel. And it confirmed the operation procedure of the fast reactor in the fuel failure.Also, the improvement items such as the improvement of the operation and the procedure and the remodeling and the service of the facilities could be picked up. In the future, it attempts these compatible, and it prepares for the MK-III reactor core operation and it incorporates a final examination result by the improvement of the safety of FBR.

JAEA Reports

Operation and maintenance experience on the fuel handling systems and storage facilities of "MONJU", 1

; ; Yamada, Takeshi; ; ; ; Kaito, Yasuaki; ; Kotaka, Yoshinori; ; et al.

PNC TN2410 96-005, 339 Pages, 1996/03

PNC-TN2410-96-005.pdf:14.53MB

Construction of the 'Monju' fuel handling systems was completed in April, 1992. From March 1991 to August 1992, pre-commissioning tests were carried out. In December 1992, all the systems of Monju were transfered to PNC, and commissioning tests and reactor physics tests, were started. For the first time, during these physics tests, the fuel handling systems were operated for one of the commissioning tests 'Loading to Criticality', without significant problems. 168 fuel sub-assemblies were loaded into the core and the first criticality was achieved on 5th April 1994. The fuel handling systems continued in operation for the 'Loading to Full Size of the Core', power distribution test and for cleaning discharged dummy sub-assemblies. To keep these fuel handling systems working somothly and satisfactorily annual maintenance has been carried out since 1992. This paper describes the operation and maintenance experience of fuel handling systems after the pre-commissioning tests and future study items for system reliability improvement.

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 5; Visual inspection and obstacle removal method in reactor vessel of the experimental fast reactor Joyo

Ito, Hideaki; Nagai, Akinori; Tobita, Shigeharu; Ashida, Takashi; Kaito, Yasuaki; Katagiri, Genichi*; Kodama, Takemitsu*; Yoshimura, Tetsuji*

no journal, , 

no abstracts in English

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 3-2; Retrieval the bent irradiation test subassembly using remote control device

Okazaki, Yoshihiro; Ashida, Takashi; Miyamoto, Kazuyuki; Kaito, Yasuaki; Ito, Hideaki

no journal, , 

no abstracts in English

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 4-3; Retrieval the bent irradiation test subassembly using remote control device, 2

Ashida, Takashi; Kaito, Yasuaki; Miyamoto, Kazuyuki; Noguchi, Koichi; Ito, Hideaki

no journal, , 

The MARICO-2 irradiation test part has been bent onto the in-vessel storage rack approximately 200 mm in horizontal length. As a result, the transfer pot in which the MARICO-2 irradiation test part has been installed can't be handled with the refueling machine. In order to confirm the condition of the bent MARICO-2 irradiation test subassembly and take the appropriate method, MARICO-2 lifting up test was conducted with a simple handling device which gripped the bent wrapper tube and lifted up the MARICO-2 irradiation test part approximately 40 mm. The test result confirmed that the MARICO-2 irradiation test part was stuck in the transfer pot due to the deformation of wrapper tube. Therefore, we will investigate the detail design of the MARICO-2 retrieval device with the fuel transfer pot and inspect whether the MARICO-2 is pulled out from the transfer pot.

Oral presentation

Oral presentation

The Experience and effect of operator education training

Kaito, Yasuaki; Suzuki, Shinya

no journal, , 

no abstracts in English

Oral presentation

Emergency procedure control for station blackout in the experimental fast reactor Joyo

Kawasaki, Toru; Sawada, Toru; Kaito, Yasuaki; Yonekawa, Mitsuru; Saito, Takakazu

no journal, , 

no abstracts in English

Oral presentation

Development of repair techniques in the reactor vessel of the experimental fast reactor Joyo; MARICO-2 S/A retrieving

Kaito, Yasuaki; Ashida, Takashi; Imaizumi, Kazuyuki; Izawa, Osamu; Naito, Hiroyuki

no journal, , 

In the experimental fast reactor Joyo, it was confirmed that the top of the irradiation test sub-assembly(S/A) of MARICO-2 (material testing rig with temperature control) had been bent onto the in-vessel storage rack as an obstacle, and the MARICO-2 S/A had been stuck in the transfer pot owing to its deformation. Since the MARICO-2 S/A cannot be retrieved with the existing handling equipment, special handling equipment was developed while considering the anomalous conditions. Emphasis had been placed on (1) how to precisely control the gripper position in the reactor vessel, and (2) how to retrieve the MARICO-2 S/A together with transfer pot with high reliability in the design and development of equipment. The MARICO-2 S/A was retrieved successfully together with transfer pot in 2014. This paper describes the in-vessel repair techniques for MARICO-2 S/A retrieval.

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