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JAEA Reports

Clearance of concrete generated from modification activities of JRR-3; Method for measuring and evaluating of radioactivity concentration

Satoyama, Tomonori; Kishimoto, Katsumi; Hoshi, Akiko; Takaizumi, Hirohide; Tsutsumi, Masahiro; Inanobe, Hiroshi; Yoshimori, Michiro

JAEA-Technology 2011-003, 53 Pages, 2011/03

JAEA-Technology-2011-003.pdf:1.6MB

In Nuclear Science Research Institute, clearance activities for extremely low-level radioactive concrete debris, which were generated from the modification activities of JRR-3 from FY 1985 to FY 1989 and now are stored in the waste storage facility NL, have been carried out in order to plan reasonable disposal and effectively reusing of concrete waste, moreover to secure storage capacity at the waste storage facilities. Method for measuring and evaluating of radioactivity concentration was applied for approval of Minister of MEXT on November 8, 2007, approved on July 25, 2008. After that the necessary equipments for clearance works were equipped and operational safety progress and manuals for clearance works were prepared. So clearance works were started in FY 2009. This report summarizes the method for measuring and evaluating of radioactivity concentration for concrete generated from modification activities of JRR-3.

Journal Articles

Development of CLEVES for clearance activities in JAEA

Tachibana, Mitsuo; Ishigami, Tsutomu; Satoyama, Tomonori; Yoshimori, Michiro

Proceedings of 2010 ANS Topical Meeting on Decommissioning, Decontamination and Reutilization & Technology Expo (DD&R 2010) (CD-ROM), p.341 - 344, 2010/08

The clearance level verification evaluation system (CLEVES) has been developed to execute clearance activities efficiently. The SNM which is one of programs of the CLEVES was fabricated for selecting nuclides for measurement and assessment (NMA) based on evaluation of relative importance measure (RIM: nuclide activity divided by clearance level) for nuclides. In addition, case study was carried out by using the SNM based on data concerning clearance activities for concrete generated from the JRR-3. In this report, outline of the CLEVES, a method for selecting NMAs in the SNM, and calculated results of case study are described.

JAEA Reports

Selection of important nuclides from the viewpoint of safety assessment for disposal of radioactive waste arising from research institutes, 2; Analytical scheme for nuclide composition in radwastes arising from research and testing reactor and post-irradiation examination facilities

Asai, Shiho; Sakai, Akihiro; Yoshimori, Michiro; Kihara, Shinji

JAERI-Tech 2003-071, 46 Pages, 2003/08

JAERI-Tech-2003-071.pdf:4.31MB

As part of survey concerning radioactive inventory of radwastes arising from research institutes, an analytical scheme has been studied for verifying their nuclide composition based on calculation analysis and record, in consideration of the its characteristics. In this study, radwastes are used as samples, which arise from research and testing reactors and post-irradiation examination facilities (PIE facilities). Though separation procedures are simplified and rationalized, quantifiable values could be obtained with relative errors under 10% for almost all the samples containing nuclides like $$^{59}$$Ni and $$^{238}$$U which concentrations are low, and recoveries were high on the whole. These show that the analytical scheme is useful for chemical separation of radwastes arising from research and testing reactors and PIE facilities.

JAEA Reports

Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

JAERI-Tech 2001-018, 88 Pages, 2001/03

JAERI-Tech-2001-018.pdf:5.66MB

no abstracts in English

Journal Articles

Deterministic approach towards establishing of clearance levels in Japan

Okoshi, Minoru; Sakai, Akihiro; Yoshimori, Michiro; Yamamoto, Hideaki; Takahashi, Tomoyuki; Kimura, Hideo

Proc. of 7th Int. Conf. on Radioactive Waste Management and Environmental Remediation (ICEM'99)(CD-ROM), 8 Pages, 1999/09

no abstracts in English

Journal Articles

Derivation methods of clearance levels for nuclear reactors

Okoshi, Minoru; Takahashi, Tomoyuki*; Kimura, Hideo; ; Sakai, Akihiro; Yoshimori, Michiro; Yamamoto, Hideaki

Hoken Butsuri, 34(2), p.187 - 197, 1999/00

no abstracts in English

Journal Articles

Integrated approach for establishing of disposal systems for highly activated waste

Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Abe, Masayoshi

Proceedings of International Waste Management Symposium '99 (Waste Manegement '99) (CD-ROM), 14 Pages, 1999/00

no abstracts in English

Journal Articles

Design concept of disposal systems for highly activated waste

Okoshi, Minoru; Abe, Masayoshi; Yoshimori, Michiro; Sakai, Akihiro

Proc. of Waste Management'98 (CD-ROM), 5 Pages, 1998/00

no abstracts in English

Journal Articles

Near surface disposal of very low level waste generated from reactor decommissioning and related safety requirements

Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi

Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00

no abstracts in English

Journal Articles

Safety demonstration test for the disposal of very low level concrete waste

Abe, Masayoshi; Okoshi, Minoru; Yoshimori, Michiro

Dekomisshoningu Giho, 0(15), p.50 - 58, 1996/12

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

Near surface disposal of VLLW from reactor decommissioning and safety requirements

Okoshi, Minoru; Yoshimori, Michiro

Proc. of 3rd Japan-Russia Joint Symp. on Radiation Safety, 0, p.75 - 85, 1995/00

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 2; Investigation of contamination situation of concrete

Tachibana, Mitsuo; Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Takaizumi, Hirohide; Yoshimori, Michiro; Okoshi, Minoru; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 3; Method for measurement and assessment of activity

Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Yoshimori, Michiro; Okoshi, Minoru; Kogure, Hiroto; Tsutsumi, Masahiro; Inanobe, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 1; Over view

Yoshimori, Michiro; Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Okoshi, Minoru; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Clearance of concrete debris generated from modification work of JRR-3, 5; Result of measurement and evaluation of radioactivity distribution

Nanri, Tomohiro; Kishimoto, Katsumi; Satoyama, Tomonori; Takaizumi, Hirohide; Kanno, Tomoyuki; Maruyama, Tatsuya; Yoshimori, Michiro

no journal, , 

no abstracts in English

Oral presentation

Clearance of concrete debris generated from modification work of JRR-3, 4; Progress of clearance work

Satoyama, Tomonori; Kishimoto, Katsumi; Nanri, Tomohiro; Takaizumi, Hirohide; Kanno, Tomoyuki; Maruyama, Tatsuya; Yoshimori, Michiro

no journal, , 

no abstracts in English

Oral presentation

Effective utilization of concrete debris generated from nuclear reactors; Clearance of concrete debris generated from modification work of JRR-3

Kishimoto, Katsumi; Satoyama, Tomonori; Takaizumi, Hirohide; Kanno, Tomoyuki; Maruyama, Tatsuya; Yoshimori, Michiro

no journal, , 

We have been storing about 4000 tons of very low-level radioactive concrete debris as radioactive wastes generated from the modification of JRR-3 between 1985 and 1990. At that time, the clearance system was not a part of our regulatory law. We conducted a preliminary survey of contamination levels, and then established procedures for measuring and evaluating the radioactivity concentration. In 2008, the government authorized our procedures for clearance. Since FY 2009, we have measured the radioactivity concentration of concrete debris, using the government-authorized procedures. By the end of FY 2012, the government had confirmed the correctness of our measurements and evaluation results on about 1900 tons of concrete debris. We processed the concrete debris that was approved by the government for recycling. By the end of FY 2012, we had reused about 600 tons of concrete debris as backfilling material in depressed areas around buildings in the Nuclear Science Research Institute.

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