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JAEA Reports

Development of gamma camera for survey of contamination distribution; Performance demonstration of gamma camera based on survey of contamination on operating floor of the Fukushima Daiichi Nuclear Power Plant Unit 2 reactor building by $$gamma$$-eyeII

Kanayama, Fumihiko; Okada, Takashi; Fukushima, Mineo; Yoshimoto, Katsunobu*; Hanyu, Toshinori; Kawanobe, Takayuki

JAEA-Technology 2013-049, 60 Pages, 2014/03

JAEA-Technology-2013-049.pdf:25.84MB

For planning of removing fuels and debris from the Unit 2 reactor building, TEPCO has already started to measure dose rate over the floor by remotely operated vehicle. Because the measured data were widely distributed in the range of several decades to one thousand mSv/h, it is necessary for TEPCO to survey of contamination distribution on operation floor 2 for more detail planning. JAEA estimated sensitivity of developed gamma camera system named "$$gamma$$-eye II" in consistency with actual radiation condition, and carried a demonstration experiment at Fukushima Daiichi N.P.P. to confirm a strength of jamming by back ground dose. Then, JAEA surveyed contamination distribution of operating floor using $$gamma$$-eye II. At the result of survey, it was found that, - main radiation source in survey area was located on upper reactor well, - western floor in survey area was lower the margin of capacity of $$gamma$$-eye II, -there was a highly contaminated spot on the floor near the opened BOP.

JAEA Reports

JRTF decommissioning project; Evaluation of project management data concerning dismantling activities of glove boxes, 1

Muraguchi, Yoshinori; Kanayama, Fumihiko; Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo

JAEA-Technology 2012-035, 69 Pages, 2012/12

JAEA-Technology-2012-035.pdf:4.96MB

Dismantling activities of equipment in JAEA's Reprocessing Test Facility (JRTF) used for wet reprocessing test started from 1996. Glove boxes and hoods installed in the main building were dismantled preferentially for securing temporary place of dismantled waste and dismantling tools by dismantling activities. Of these, 8 glove boxes (glove box group) were installed in room 232 of the main building. The glove box group was dismantled by setting up a large plastic enclosure (greenhouse) for work efficiency. In this report, dismantling procedure and actual data obtained from dismantling activity were arranged about dismantling activity of glove box group of room 232 in 1996. About dismantling activity of glove box group, manpower of the basic work items extracted by classifying into common work items and independent work items were analyzed. In addition, calculation equation was examined concerning dismantling of glove boxes.

Journal Articles

Decontamination experiment for floor of Fukushima Daiichi reactor building

Kanayama, Fumihiko; Hayashi, Takehiro; Kawatsuma, Shinji

Proceedings of American Nuclear Society Embedded Topical on Decommissioning, Decontamination and Reutilization and Technology Expo (DD&R 2012) (DVD-ROM), p.14 - 15, 2012/06

no abstracts in English

JAEA Reports

Removal of the liquid waste storage tank LV-2 in JRTF, 2; Removal works

Kanayama, Fumihiko; Hagiya, Kazuaki; Sunaoshi, Mizuho; Muraguchi, Yoshinori; Satomi, Shinichi; Nemoto, Koichi; Terunuma, Akihiro; Shiraishi, Kunio; Ito, Shinichi

JAEA-Technology 2011-011, 36 Pages, 2011/06

JAEA-Technology-2011-011.pdf:2.53MB

Dismantling activities of equipments in JAERI's Reprocessing Test Facility (JRTF) started from 1996 as a part of decommissioning of this facility. Removing out of the large liquid waste storage tank LV-2 as a whole tank without cutting in pieces from the annex building B to confirm safety and efficiency of this method started from 2006. After preparatory works, ceiling of LV-2 room was opened, and LV-2 was transferred. Useful data were collected on manpower, radiation control and waste amount through the preparatory works, and work efficiency was analyzed by use of these data.

Journal Articles

Dismantling method of fuel cycle facilities obtained by dismantling of the JRTF

Kanayama, Fumihiko

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.415 - 422, 2010/10

With the development of researches and investigations for atomic energy in Japan, various nuclear institutes have been built since 1960s. Today, large numbers of nuclear institutes became old and should be dismantled near future. Necessities for dismantling technology for atomic institutes became large. To dismantle atomic institutes, many cost and time are required. By choosing appropriate method, the cost and time for dismantling can be decreased. To choose appropriate method, it is important to collect the dismantling data of each kind of method, and understand advantages and disadvantages of each dismantling method accurately. To plan the nuclear facility which can be dismantled easily, and to promote setting up and dismantling efficiently, it is important to understand advantages and disadvantages of each dismantling method accurately, too. In JAEA, JPDR was dismantled to get experience of dismantling method of nuclear reactor. But, JAEA did not have experience of fuel cycle facility. Dismantling cost of fuel cycle facilities are more than that of nuclear facilities due to the contamination by TRU nuclide in fuel cycle facilities, In this report, to find appropriate method for dismantling fuel cycle facility, we dismantled liquid waste storage tank and wall-penetrating pipings in JRTF, which was one of the reprocessing facilities in JAEA. Number of man-days and occupational dose required were estimated to reveal advantages and disadvantages of two dismantling methods in each component. Moreover, appropriate conditions to select these dismantling methods are introduced.

JAEA Reports

Removal of the liquid waste storage tank LV-2 in JRTF, 1; Preparatory works

Satomi, Shinichi; Kanayama, Fumihiko; Hagiya, Kazuaki; Myodo, Masato; Kobayashi, Tadayoshi; Tomii, Hiroyuki; Tachibana, Mitsuo

JAEA-Technology 2008-067, 53 Pages, 2008/10

JAEA-Technology-2008-067.pdf:8.66MB

Dismantling activities of equipments in JAERI's Reprocessing Test Facility (JRTF) started from 1996 as a part of decommissioning of this facility. The large liquid waste storage tank LV-2 is scheduled to remove out as a whole tank without cutting in pieces from the annex building B to confirm safety and efficiency of this method from 2006. Before removal of the LV-2 tank, some preparatory works were carried out such as opening of concrete wall (LV-2 room) for the entrance of workers and materials, removal of pipes connected to the LV-2 tank, and decontamination of radioactive sludge in the LV-2 tank. Useful data were collected on manpower, radiation control and waste amount through the preparatory works, and work efficiency was analyzed by use of these data. It was compared manpower between core boring and hand-breaker crushing activities in the concrete wall opening work. It was also confirmed that local exposure of worker could be reduced in large extent by an addition of vinyl chloride cover on worker's ventilated suit.

Oral presentation

Production of plastic scintillation survey meter for clearance verification measurement

Tachibana, Mitsuo; Myodo, Masato; Shiraishi, Kunio; Kanayama, Fumihiko; Kobayashi, Tadayoshi; Ishigami, Tsutomu; Tomii, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

One piece removal of liquid waste storage tank LV-2, 1; Preparation

Kanayama, Fumihiko; Satomi, Shinichi; Myodo, Masato; Tomii, Hiroyuki; Tachibana, Mitsuo

no journal, , 

no abstracts in English

Oral presentation

Characteristics of decommissioning of nuclear facilities

Kanayama, Fumihiko; Nemoto, Koichi; Shiraishi, Kunio; Ito, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Summary and lesson learned on nuclear disaster robots of JAEA in the accident at Fukushima Daiichi Nuclear Power Station

Okada, Takashi; Kawatsuma, Shinji; Fukushima, Mineo; Igarashi, Miyuki; Nakai, Koji; Mimura, Ryuji; Kanayama, Fumihiko

no journal, , 

Due to Tohoku Pacific Ocean earthquake and tsunami in 11 March in 2011, Tokyo Electric Power Co. Fukushima Daiichi Nuclear Power Station lost all power and has occurred accidents for failure of core cooling function. In Japan Atomic Energy Agency it was remodeled the nuclear disaster robot, was developed $$gamma$$-ray visualization equipment and has been supporting the accident recovery. This paper is described the lessons learned from the supporting with the nuclear disaster robots and the $$gamma$$-ray visualization equipment.

Oral presentation

Remote operation technology applied for the Fukushima Daiichi Nuclear Power Plant accident, 1; Summary on activities of remote operation technology in JAEA

Kawatsuma, Shinji; Okada, Takashi; Fukushima, Mineo; Nakai, Koji; Mimura, Ryuji; Kanayama, Fumihiko

no journal, , 

no abstracts in English

Oral presentation

Remote operation technologies applied for the Fukushima Daiichi Nuclear Power Plant accident, 3; Development of $$gamma$$ ray imaging system and reconnaissance platform

Mimura, Ryuji; Kanayama, Fumihiko; Okada, Takashi; Kawatsuma, Shinji

no journal, , 

no abstracts in English

Oral presentation

Decontamination experiment for floor of Fukushima Dai-ichi Reactor Buildings, 1; Decontamination basic experiment using non radioactive Cs

Kanayama, Fumihiko; Hayashi, Takehiro; Sato, Isamu; Kawatsuma, Shinji; Fukushima, Mineo

no journal, , 

no abstracts in English

Oral presentation

Decontamination experiment for floor of Fukushima Dai-ichi Reactor Buildings, 2; Penetration behavior of simulated-contaminated water into floor and wall materials

Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.

no journal, , 

no abstracts in English

Oral presentation

Penetration behavior of a solution containing radioactive nuclides into concrete and epoxy resin paint

Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurement of contamination distribution for operating floor of the Fukushima Daiichi Unit 2 reactor building by $$gamma$$ camera, 2; Performance verification of the $$gamma$$ camera by pre-test

Okada, Takashi; Kanayama, Fumihiko; Fukushima, Mineo; Yoshimoto, Katsunobu; Hanyu, Toshinori; Kawanobe, Takayuki; Takahashi, Yoshiaki*; Oikawa, Kageharu*; Matsumoto, Yasuhiro*; Kishi, Kazuyoshi*; et al.

no journal, , 

In order to measure contamination distribution for operating floor of the Fukushima Daiichi Unit 2 reactor building by the $$gamma$$ camera which JAEA developed, the trial examination which determines a measurement condition was done.

Oral presentation

Measurement of contamination distribution for operating floor of the Fukushima Daiichi Unit 2 reactor building by $$gamma$$ camera, 3; Measurement and analysis

Fukushima, Mineo; Okada, Takashi; Kanayama, Fumihiko; Yoshimoto, Katsunobu; Hanyu, Toshinori; Kawanobe, Takayuki; Takahashi, Yoshiaki*; Oikawa, Kageharu*; Matsumoto, Yasuhiro*; Kishi, Kazuyoshi*; et al.

no journal, , 

Contamination distribution for operating floor of the Fukushima Daiichi Nuclear Power Plant was measured from opened blow out panel using $$gamma$$ viewer "$$gamma$$-eyeII" developed by JAEA. It is obtained that one of the main contaminated area is on the reactor well and contamination level of the surface of west side floor is lower than lower limit level of detector.

Oral presentation

Atmosphere measurement by compact Raman Lidar under nuclear environment

Chigira, Tomoyuki*; Shiina, Tatsuo*; Saito, Hayato*; Manago, Naohiro*; Kuze, Hiroaki*; Hanyu, Toshinori; Kanayama, Fumihiko; Fukushima, Mineo

no journal, , 

The compact Raman Lidar is developed for the atmosphere measurement under nuclear environment, in which radiation ionize the water vapor and generate the water-cluster. In this study, the Raman lidar throws the NUV-beam of 349 nm and detects the backscattering echoes of water-Raman (396 nm) and the water-vapor-Raman (400 nm). Am-241 of 9 MBq was used for the radiation source. The results showed that the water-Raman increased and the water-vapor-Raman decreased under the nuclear environment. Its ratio becomes 3 times. It is well coincide with the estimation. The radius of water cluster was estimated 200 nm by the experiment.

Oral presentation

Compact Raman lidar measurement of liquid and vapor phase water under the influence of ionizing radiation

Shiina, Tatsuo*; Chigira, Tomoyuki*; Saito, Hayato*; Manago, Naohiro*; Kuze, Hiroaki*; Hanyu, Toshinori; Kanayama, Fumihiko; Fukushima, Mineo

no journal, , 

22 (Records 1-20 displayed on this page)