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JAEA Reports

Design and production of the valve used in Radioactive Liquid Disposal Facility

Nishimura, Arashi; Okada, Yuji; Sugaya, Naoto; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi

JAEA-Technology 2021-003, 51 Pages, 2021/05

JAEA-Technology-2021-003.pdf:5.55MB

In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, obtain the approval of the JAEA to the design and construction method from JFY2016, the tanks and pipes were replaced from JFY2016 to 2019. In the replaced, the production of the tanks and pipes of the liquid waste disposal facility applied Japanese technical standards correspondingly. On the other hand, the valve did not fall under the category of Japanese technical standards. The manufacturing specifications when replacing the valve were decided based on the including the selecting the standards of production and inspection for valves, Fluid properties, experience in JMTR. The production proceeded while carrying out the decided inspection. The valves that passed all the inspections were installed together with the tanks and pipes of the liquid waste, and the finished inspection was performed as a systems. The construction was completed with those inspection passed. This report is summarized valve Design, production and installation.

JAEA Reports

Soundness survey of cooling tower of Utility Cooling Loop (UCL Cooling Tower) in JMTR

Oto, Tsutomu; Asano, Norikazu; Kawamata, Takanori; Yanai, Tomohiro; Nishimura, Arashi; Araki, Daisuke; Otsuka, Kaoru; Takabe, Yugo; Otsuka, Noriaki; Kojima, Keidai; et al.

JAEA-Review 2020-018, 66 Pages, 2020/11

JAEA-Review-2020-018.pdf:8.87MB

A collapse event of the cooling tower of secondary cooling system in the JMTR (Japan Materials Testing Reactor) was caused by the strong wind of Typhoon No.15 on September 9, 2019. The cause of the collapse of the cooling tower was investigated and analyzed. As the result, it was identified that four causes occurred in combination. Thus, the soundness of the cooling tower of Utility Cooling Loop (UCL cooling tower), which is a wooden cooling tower installed at the same period as the cooling tower of secondary cooling system, was investigated. The items of soundness survey are to grasp the operation conditions of the UCL cooling tower, to confirm the degradation of structural materials, the inspection items and inspection status of the UCL cooling tower, and to investigate the past meteorological data. As the results of soundness survey of the UCL cooling tower, the improvement of inspection items of the UCL cooling tower was carried out and the replacement and repair of the structural materials of the UCL cooling tower were planned for safe maintenance and management of this facility. And the renewal plan of new cooling tower was created to replace the existing UCL cooling tower. This report is summarized the soundness survey of the UCL cooling tower.

JAEA Reports

Validation of repairing method for concrete wall of the JMTR tank-yard building

Sugaya, Naoto; Okada, Yuji; Nishimura, Arashi; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi

JAEA-Testing 2020-004, 67 Pages, 2020/08

JAEA-Testing-2020-004.pdf:8.17MB

In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, the tanks and pipes were replaced from JFY2016 to 2019. On the other hand, a lot of cracks were occurred on the concreate wall of the tank-yard building when the frame structure supports were fixed to the concrete wall in the replacement work. Thus, it is necessary to repair the concreate wall of the tank-yard building. Especially, some cracks with swelling (cone-shaped fracture) were raised around some anchor bolts (the post-installed chemical anchor bolts) fixed the frame structure supports. The repairing method for the cone-shaped fracture of the concrete wall is standardized, but there was no reference value of tensile strength for the validation of the post-installed chemical anchor bolts after the repairing method. In this report, the repairing method was selected for the cone-shaped fracture on the concreate wall and the reference value of tensile strength for the validation of the post-installed chemical anchor bolts by this repairing method. The mock-ups for repairing cone-shaped fracture were fabricated by the selected repairing method and the tensile tests of the post-installed chemical anchor bolts were performed. From the results, the validation of the repairing method was obtained in this test and it was obvious the repairing of cone-shaped fracture is preferable method for the concreate wall of the JMTR tank-yard building.

Journal Articles

Status of JMTR decommissioning plan formulation, 2

Otsuka, Kaoru; Ide, Hiroshi; Nagata, Hiroshi; Omori, Takazumi; Seki, Misaki; Hanakawa, Hiroki; Nemoto, Hiroyoshi; Watanabe, Masao; Iimura, Koichi; Tsuchiya, Kunihiko; et al.

UTNL-R-0499, p.12_1 - 12_8, 2019/03

no abstracts in English

JAEA Reports

Investigation on integrity of the surge tank, the degas tank and the purify water tank for the primary cooling system of JMTR

Nemoto, Hiroyoshi; Ebisawa, Hiroyuki; Ogasawara, Yasushi; Echigoya, Shinichi

JAEA-Review 2010-018, 32 Pages, 2010/07

JAEA-Review-2010-018.pdf:2.07MB

An integrity investigation was carried out for the JMTR reactor installations, which were the primary cooling system tanks (the surge tank, the degas tank and the purify water tank) and they would be used for the long term after JMTR restart, before the renewal work for the JMTR on FY2007. The visual inspection and the liquid penetrate test (PT) were carried out as the integrity investigation to confirm the integrity of primary cooling system tanks. In order to use the surge tank, the degas tank and the purify water tank continuously for long term, it is important for maintaining the integrity of the surge tank, the degas tank and the purify water tank by the periodical maintenance and the repairing work.

JAEA Reports

The Outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Oto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; et al.

JAEA-Technology 2009-030, 165 Pages, 2009/07

JAEA-Technology-2009-030.pdf:69.18MB

The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation.

Oral presentation

Refurbishment and restart of JMTR, 3; Investigation of integrity of reactor facilities, 2; Primary cooling system heat exchanger and tanks

Koike, Sumio; Onoue, Ryuji; Ebisawa, Hiroyuki; Nemoto, Hiroyoshi; Takahashi, Kunihiro; Kaminaga, Masanori

no journal, , 

no abstracts in English

Oral presentation

Renovation of instrumentation and control system of JMTR

Nemoto, Hiroyoshi; Ebisawa, Hiroyuki; Takahashi, Masayoshi*; Ihara, Yoshihisa*; Ogasawara, Yasushi; Echigoya, Shinichi

no journal, , 

JMTR (Japan Materials Testing Reactor) has started refurbishment of reactor facilities from FY2007, and the renewed and upgraded JMTR will start from FY2011. Control system of the JMTR has been used for 42 years since first criticality in 1968. Distributed control system (DCS) introduced in this project will enable the operators to monitor and control the entire plant information on a unified platform and realize digitalization / integration of various data. In addition, adoption of large screens will make it possible to show versatile information collectively, and it will lead to increase operability, visibility and assistance for plant operators. For the reactor control room, new layout design is introduced based on desired ergonomics. This report summarizes the outline of refurbishment project on plant control upgrading from analog control panels to the latest distributed control system (DCS).

Oral presentation

Renewal of JMTR of facility, 3; Renewal of instrumentation and control systems

Oto, Tsutomu; Nemoto, Hiroyoshi; Kimura, Tadashi; Watahiki, Shunsuke; Hasegawa, Teiji; Ouchi, Takuya; Echigoya, Shinichi; Fukasaku, Akitomi

no journal, , 

no abstracts in English

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