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JAEA Reports

Experience and technology consolidation related to dismantling sodium equipment; Technology to reduce sodium remaining in 100m$$^{3}$$ grade large tanks

Hayakawa, Masato; Shimoyama, Kazuhito; Miyakoshi, Hiroyuki; Suzuki, Shigeaki*

JAEA-Technology 2021-027, 33 Pages, 2022/01

JAEA-Technology-2021-027.pdf:3.64MB

At the Oarai Research and Development Institute of the Japan Atomic Energy Agency, experimental studies in various sodium environments are being conducted in connection with the research and development of sodium-cooled fast reactors such as the experimental fast reactor Joyo and the prototype fast reactor Monju. The dismantling of sodium test facilities and equipment that have achieved their purpose has been carried out sequentially, and a wealth of experience and technology has been accumulated. On the other hand, a large amount of metallic sodium used for research and testing is being reused for new testing facilities, and the large sodium tanks that contained the metallic sodium are being dismantled. In order to dismantle these tanks safely and efficiently, it is important to reduce the residual sodium inside the tanks (especially at the bottom) as much as possible before dismantling. Therefore, we have been working on the reduction of residual sodium at the bottom of several large sodium tanks of 100 m$$^{3}$$ class. This report describes the technologies and experiences related to the reduction of residual sodium that have been carried out so far.

Journal Articles

Status of decommissioning of the Plutonium Fuel Fabrication Facility and R&Ds of dismantling technologies for gloveboxes

Kimura, Yasuhisa; Hirano, Hiroshi; Watahiki, Masatoshi; Kuba, Meiji; Ishikawa, Shinichiro

Dekomisshoningu Giho, (52), p.45 - 54, 2015/09

The Plutonium Fuel Fabrication Facility (PFFF) of the Japan Atomic Energy Agency is now in its decommissioning phase. In the PFFF, terminated gloveboxes have been dismantled. Gloveboxes to be dismantled are surrounded by a plastic enclosure to prevent contamination from being spread into process room. Dismantling operations for gloveboxes are performed manually by workers, each wearing an air-feed suit. However, the mental and physical loads placed on workers wearing the air-feed suits are intensively high. Therefore, R&Ds on new dismantling technologies including utilization of heavy machines covered with plastic enclosure for anti-contamination have been started to reduce the potential risks associated with workers and decommissioning costs. In this paper, the status of decommissioning of the PFFF and the overview of developed dismantling technologies for $$alpha$$-tight gloveboxes are described.

Journal Articles

The mock-up test of remote controlled dismantling apparatus for large-sized vessels

Myodo, Masato; Okane, Shogo; Miyajima, Kazutoshi

Dekomisshoningu Giho, (23), p.2 - 16, 2001/03

no abstracts in English

JAEA Reports

None

Tanimoto, Kenichi

PNC TN9450 97-002, 504 Pages, 1996/12

no abstracts in English

Journal Articles

Summary and results of the JPDR dismantling project

Miyasaka, Yasuhiko

Dekomisshoningu Giho, 0(14), p.24 - 33, 1996/08

no abstracts in English

Journal Articles

Results and outline of JPDR dismantling demonstration project

Miyasaka, Yasuhiko; ; Tanaka, Mitsugu; Nakamura, Hisashi; ; Tachibana, Mitsuo; ; Hatakeyama, Mutsuo; ; Yoshimori, Michiro; et al.

Nihon Genshiryoku Gakkai-Shi, 38(7), p.553 - 576, 1996/00

no abstracts in English

Journal Articles

Dismantling of the EBWR's activated components

RANDEC Nyusu, 0(27), p.6 - 7, 1995/10

no abstracts in English

Journal Articles

Dismantling of Japan Power Demonstration Reactor (JPDR)

Miyasaka, Yasuhiko

Enerugi Rebyu, 15(9), p.11 - 15, 1995/00

no abstracts in English

Journal Articles

Decommissioning program for JAERI's reprocessing test facility

; Nemoto, Koichi; ; Miyajima, Kazutoshi; Ito, Akira*

IMechE Conf. Trans., Int. Conf. on Nuclear Decommissioning, 0, p.229 - 235, 1995/00

no abstracts in English

Journal Articles

Development of method for decontaminating concrete surface by laser treatment

Kamata, Hirofumi*; Mimori, Takeo; *; Sivakumaran, W.*; *; Ito, Akira*

Nuclear Decom '95 (Poster Session), 1 Pages, 1995/00

no abstracts in English

Journal Articles

The design and manufacturing of remote dismantling apparatus for large vessel

Mimori, Takeo; Kumagai, Norio*

Nuclear Decom '95 (Poster Session), 2 Pages, 1995/00

no abstracts in English

Journal Articles

Treatment program for liquid waste in JAERI's reprocessing test facility

Okane, Shogo; Miyajima, Kazutoshi; Takahashi, Hideki;

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1905 - 1908, 1995/00

no abstracts in English

Journal Articles

Progress with tests on melting of low-level metallic waste at JAERI

Fujiki, Kazuo;

EUR-15691, 0, p.133 - 146, 1994/00

no abstracts in English

JAEA Reports

None

; Nakano, Tomoyuki; *; *; Asami, Makoto*; Tanimoto, Kenichi; Enokido, Yuji

PNC TN9080 92-001, 107 Pages, 1992/01

PNC-TN9080-92-001.pdf:2.24MB

None

Journal Articles

Removal of JPDR biological shield concrete using diamond sawing and coring system

Hoshi, Tatsuo; ; *; *; *; *; *; *

FAPIG, 0(129), p.28 - 32, 1991/11

no abstracts in English

Journal Articles

Reactor decommissioning technology development and actual dismantling of JPDR

Genshiryoku Shisetsu Dekomisshoningu Gijutsu, p.39 - 75, 1991/00

no abstracts in English

Journal Articles

Decommissioning of reactor and recycling of low level waste materials

Fujiki, Kazuo

Kinzoku, 60(9), p.31 - 35, 1990/09

no abstracts in English

JAEA Reports

Determination of the long-lived nuclides in biological shielding concrete, ion exchange resine and fuel storage pool water of JPDR

Takeishi, Hideyo; ; ; Kono, Nobuaki; ; Yonezawa, Chushiro; Hatakeyama, Mutsuo;

JAERI-M 89-224, 45 Pages, 1990/01

JAERI-M-89-224.pdf:1.13MB

no abstracts in English

27 (Records 1-20 displayed on this page)