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JAEA Reports

Disassembly of JT-60 tokamak device and ancillary facilities for JT-60 tokamak

Okano, Fuminori; Ichige, Hisashi; Miyo, Yasuhiko; Kaminaga, Atsushi; Sasajima, Tadayuki; Nishiyama, Tomokazu; Yagyu, Junichi; Ishige, Yoichi; Suzuki, Hiroaki; Komuro, Kenichi; et al.

JAEA-Technology 2014-003, 125 Pages, 2014/03

JAEA-Technology-2014-003.pdf:13.32MB

The disassembly of JT-60 tokamak device and its peripheral equipments, where the total weight was about 5400 tons, started in 2009 and accomplished in October 2012. This disassembly was required process for JT-60SA project, which is the Satellite Tokamak project under Japan-EU international corroboration to modify the JT-60 to the superconducting tokamak. This work was the first experience of disassembling a large radioactive fusion device based on Radiation Hazard Prevention Act in Japan. The cutting was one of the main problems in this disassembly, such as to cut the wielded parts together with toroidal field coils, and to cut the vacuum vessel into two. After solving these problems, the disassembly completed without disaster and accident. This report presents the outline of the JT-60 disassembly, especially tokamak device and ancillary facilities for tokamak device.

JAEA Reports

Disassembly of JT-60 tokamak device

Okano, Fuminori; Ikeda, Yoshitaka; Sakasai, Akira; Hanada, Masaya; Ichige, Hisashi; Miyo, Yasuhiko; Kaminaga, Atsushi; Sasajima, Tadayuki; Nishiyama, Tomokazu; Yagyu, Junichi; et al.

JAEA-Technology 2013-031, 42 Pages, 2013/11

JAEA-Technology-2013-031.pdf:18.1MB

The disassembly of JT-60 tokamak device and its peripheral equipments, where the total weight was about 6200 tons, started in 2009 and accomplished in October 2012. This disassembly was required process for JT-60SA project, which is the Satellite Tokamak project under Japan-EU international corroboration to modify the JT-60 to the superconducting tokamak. This work was the first experience of disassembling a large radioactive fusion device based on Radiation Hazard Prevention Act in Japan. The cutting was one of the main problems in this disassembly, such as to cut the wielded parts together with toroidal field coils, and to cut the vacuum vessel into two. After solving these problems, the disassembly completed without disaster and accident. This report presents the outline of the JT-60 disassembly, especially tokamak device.

Journal Articles

None

Yoshida, Michihiro; Miyo, Hiroaki; ; Ishibashi, Yuzo;

Saikuru Kiko Giho, (10), p.43 - 49, 2001/03

None

JAEA Reports

Measures of closing report of outside waste storage pits separate volume part II; Data collections about measurement of contamination and measurement after decontamination in outside waste storage pits

; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Yoshida, Michihiro; ; *; Miyo, Hiroaki

JNC TN8440 2000-022, 180 Pages, 2000/10

JNC-TN8440-2000-022.pdf:12.16MB

At outside waste strage pits, containers for strage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Technology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessary instruments started. Decontamination of the pits started from the beginning of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the dircumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition to above, the amount of concrete poured into the pits was about 1,200 m$$^{3}$$. These data compiled the inspection of contamination in measures of closing of the pits.

JAEA Reports

Measures of closing report of outside waste storage pits; Separate Volume Part I; Photographs sbout improvement step of outside waste storage pits

Yoshida, Michihiro; Suzuki, Satoshi*; Sukegawa, Yasuhiro*; Miyo, Hiroaki

JNC TN8440 2000-021, 180 Pages, 2000/10

JNC-TN8440-2000-021.pdf:42.37MB

At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessaly instruments started. Decontamination of the pits started fiom the beginning of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition to above, the amount of concrete poured into the pits was about 1,200 m$$^{3}$$. This report compiled the photographs of the works from confirmation of stay water at August, 1997 by finish of measures of closing of the pits at September, 2000.

JAEA Reports

Measures of closing report of outside waste storage pits

; Ishibashi, Yuzo; Yoshida, Michihiro; Miyo, Hiroaki; Sukegawa, Yasuhiro*; *; Suzuki, Satoshi*

JNC TN8440 2000-020, 500 Pages, 2000/10

JNC-TN8440-2000-020.pdf:25.91MB

At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessary instruments started. Decontamination of the pits started from the begining of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition t0 above, the amount of concrete poured into the pits was about 1,200 m$$^{3}$$.

JAEA Reports

None

Miyo, Hiroaki; ; Kudo, Kenji; Sukegawa, Yasuhiro*

JNC TN8440 99-005, 864 Pages, 1999/03

JNC-TN8440-99-005.pdf:40.45MB

None

JAEA Reports

None

Miyo, Hiroaki; Yoshida, Michihiro; *; Asami, Makoto*; Iso, Takahito*; *; *

PNC TN8440 96-010, 171 Pages, 1996/03

PNC-TN8440-96-010.pdf:9.98MB

None

JAEA Reports

None

Ouchi, Masaru; ; Sukegawa, Yasuhiro*; Miyo, Hiroaki;

PNC TN8410 91-176, 14 Pages, 1991/12

PNC-TN8410-91-176.pdf:0.5MB

None

JAEA Reports

None

Kashiro, Kashio; Miyo, Hiroaki; Asano, Takashi; *; Shinada, Masanori*; *; Oshima, Hirofumi

PNC TN8410 90-054, 203 Pages, 1990/05

PNC-TN8410-90-054.pdf:9.43MB

None

JAEA Reports

None

Oshima, Hirofumi; Miyo, Hiroaki; Asano, Takashi; Kashiro, Kashio; *; Shinada, Masanori*; *

PNC TN8410 89-015, 41 Pages, 1989/02

PNC-TN8410-89-015.pdf:1.23MB

None

JAEA Reports

None

*; Kagawa, Akio; Miyo, Hiroaki*; *; *; *; *; *

PNC TN841 84-17, 79 Pages, 1984/03

PNC-TN841-84-17.pdf:1.9MB

no abstracts in English

JAEA Reports

None

*; Miyo, Hiroaki*; *; *; Maeda, Katsuo; *; *; Kagawa, Akio

PNC TN841 83-50, 28 Pages, 1983/07

PNC-TN841-83-50.pdf:0.52MB

no abstracts in English

JAEA Reports

Developments in the treatment of solid alpha-bearing wastes at the PNC plutonium fuel facilities

*; Miyo, Hiroaki*; Ouchi, Yoshifusa; *; *

PNC TN841 78-09, 15 Pages, 1978/01

PNC-TN841-78-09.pdf:0.55MB

Some results of experiments donein PNC are presented on volume reduc-tion technics for alpha-bearing wastes. A pilot wood milling machine automatically mills the plywood frames of nipple connected HEPA filters, which result in fine sized wooden chips, two nipples and the filter components. The filter components are melted in an induction furnace to be homogeneous solids. These methods and incineration of wooden chips reduce the stored volume of HEPA filters to 1/50$$sim$$1/100. PVC and neoprene rubber are decomposed in concentrated sulfuricacid, followed by oxidation with nitric acid. The acid digestion process generates chlorine-rich gas, from which only chlorine is selectively absorbed in water. An alpha-bearing vessel and aglove box are cut at their installed places without spread of plutonium contamination outside the greenhouses. *Presented at the Joint NEA/IAEA Technical Seminar on the Treatment, Conditioning and Storage of Solid Alpha-Bearing Wastes and CladdingHulls Paris, December 5-7, 1977

JAEA Reports

None

*; *; Ouchi, Jin; Miyo, Hiroaki*

PNC TN841 77-37, 77 Pages, 1977/07

PNC-TN841-77-37.pdf:1.45MB

no abstracts in English

JAEA Reports

None

*; *; Ouchi, Jin; Miyo, Hiroaki*

PNC TN841 77-32, 120 Pages, 1977/06

PNC-TN841-77-32.pdf:3.61MB

no abstracts in English

JAEA Reports

Alpha waste management (Solid waste); Conceptual design for improvement of the Incinerator

*; *; *; *; Ouchi, Jin; Miyo, Hiroaki*

PNC TN842 77-01, 42 Pages, 1977/01

PNC-TN842-77-01.pdf:2.74MB

None

JAEA Reports

None

*; *; Ouchi, Jin; Miyo, Hiroaki*

PNC TN841 76-43, 85 Pages, 1976/10

PNC-TN841-76-43.pdf:4.05MB

no abstracts in English

JAEA Reports

Management of plutonium contaminated wastes at the plutoniumu fuel facilities in PNC

*; Miyo, Hiroaki*; Ouchi, Jin; *; *; Akutsu, Shigeru*

PNC TN841 76-53, 19 Pages, 1976/08

PNC-TN841-76-53.pdf:0.51MB

(IAEA/NEA Internatisnal symposium on the management of radioactive waster from the nuclear fuel cycle Vienne from 22 to 26 March 1976 *757) A summary is presented concerning the experiene in the management of Pu contaminated wastes at the plutonium fuel facilities of the power reactor and nuclear fuel development corporation (P.N.C). Description are given of waste generation, current handling techniques, Pu measurement techniques and process techniques now under research and development such as incineration system and a closed cycle liquid waste treatment by using decomposition of ammonium nitrate contined in the liquid.

JAEA Reports

Management of Plutonium-contaminated wastes at the Plutonium fuel facilities in PNC

*; Ouchi, Jin; Miyo, Hiroaki*; *; *; *

PNC TN841 76-07, 19 Pages, 1976/02

PNC-TN841-76-07.pdf:0.32MB

A summary is presented concerning the experience in themanagement of Pu contaminated wastes at the plutonium fuelfacilities of the Power Reactor and Nuclear Fuel DevelopmentCorporation (PNC). Deseription are given of waste generation,current handling techniques,Pu measurement techniques andprocess techniques now under research and development such asincineration system and a closed cycle liquid waste treatment byusing decomposition of ammonium nitrate contained in the liquid.

22 (Records 1-20 displayed on this page)