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JAEA Reports

Pretreatment works for disposal of radioactive wastes produced by research activities, 1

Ishihara, Keisuke; Yokota, Akira; Kanazawa, Shingo; Iketani, Shotaro; Sudo, Tomoyuki; Myodo, Masato; Irie, Hirobumi; Kato, Mitsugu; Iseda, Hirokatsu; Kishimoto, Katsumi; et al.

JAEA-Technology 2016-024, 108 Pages, 2016/12

JAEA-Technology-2016-024.pdf:29.74MB

Radioactive isotope, nuclear fuel material and radiation generators are utilized in research institutes, universities, hospitals, private enterprises, etc. As a result, various low-level radioactive wastes (hereinafter referred to as non-nuclear radioactive wastes) are produced. Disposal site for non-nuclear radioactive wastes have not been settled yet and those wastes are stored in storage facilities of each operator for a long period. The Advanced Volume Reduction Facilities (AVRF) are built to produce waste packages so that they satisfy requirements for shallow underground disposal. In the AVRF, low-level beta-gamma solid radioactive wastes produced in the Nuclear Science Research Institute are mainly treated. To produce waste packages meeting requirements for disposal safely and efficiently, it is necessary to cut large radioactive wastes into pieces of suitable size and segregate those depending on their types of material. This report summarizes activities of pretreatment to dispose of non-nuclear radioactive wastes in the AVRF.

Journal Articles

The Verification tests of the melting conditions for homogenization of metallic LLW at the JAEA

Nakashio, Nobuyuki; Osugi, Takeshi; Iseda, Hirokatsu; Tohei, Toshio; Sudo, Tomoyuki; Ishikawa, Joji; Mitsuda, Motoyuki; Yokobori, Tomohiko; Kozawa, Kazushige; Momma, Toshiyuki; et al.

Journal of Nuclear Science and Technology, 53(1), p.139 - 145, 2016/01

 Times Cited Count:1 Percentile:14.27(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Improvement for the stable operation in the super compactor

Sudo, Tomoyuki; Mimura, Ryuji; Ishihara, Keisuke; Satomi, Shinichi; Myodo, Masato; Momma, Toshiyuki; Kozawa, Kazushige

JAEA-Technology 2011-015, 24 Pages, 2011/06

JAEA-Technology-2011-015.pdf:2.28MB

The super compactor in the Advanced Volume Reduction Facilities (AVRF) treats metal wastes mainly generated from research reactors in the Nuclear Science Research Institute of JAEA. Those wastes are compacted from one third to one fourth with maximum 2,000-ton force. In the trial operation using simulated wastes, some technical problems were found to be improve for the stable operation. One problem is the motion mechanism for carrying wastes before and after compaction. The other problem is the mechanism for treating the irregular supercompacted products. In this report, we describe the detail and the result of improvement on those problems for the stable operation in the super compactor.

JAEA Reports

Evaluation of void ratio of the solidified wastes containing supercompacted wastes

Sudo, Tomoyuki; Nakashio, Nobuyuki; Osugi, Takeshi; Mimura, Ryuji; Ishihara, Keisuke; Satomi, Shinichi; Myodo, Masato; Momma, Toshiyuki; Kozawa, Kazushige

JAEA-Technology 2010-041, 38 Pages, 2011/01

JAEA-Technology-2010-041.pdf:4.73MB

The super compactor in the AVRF treats compactible metal wastes mainly generated from research reactors in the Nuclear Science Research Institute of JAEA. Those wastes are compacted with the maximum about 2,000-ton force. The supercompacted wastes are packed into the container and then immobilized with cementitious materials. The solidified wastes (containing supercompacted wastes) become an object for near surface disposal with artificial barrier. For disposal, the solidified wastes must be satisfied the technical criteria. One of the important indicators is the void ratio in the solidified wastes. In this report, we manufactured the supercompacted wastes with the ordinary treatment method for actual wastes treated in the AVRF and immobilized with a mortar grout. The void ratio of the solidified wastes were evaluated in consideration for concrete vault disposal. As a result, We confirmed the integrity of the solidified wastes from a point of view of void ratio.

JAEA Reports

Construction, management and operation on advanced volume reduction facilities

Higuchi, Hidekazu; Osugi, Takeshi; Nakashio, Nobuyuki; Momma, Toshiyuki; Tohei, Toshio; Ishikawa, Joji; Iseda, Hirokatsu; Mitsuda, Motoyuki; Ishihara, Keisuke; Sudo, Tomoyuki; et al.

JAEA-Technology 2007-038, 189 Pages, 2007/07

JAEA-Technology-2007-038-01.pdf:15.13MB
JAEA-Technology-2007-038-02.pdf:38.95MB
JAEA-Technology-2007-038-03.pdf:48.42MB
JAEA-Technology-2007-038-04.pdf:20.53MB
JAEA-Technology-2007-038-05.pdf:10.44MB

The Advanced Volume Reduction Facilities (AVRF) is constructed to manufacture the waste packages of radioactive waste for disposal in the Nuclear Science Research Institute of the Japan Atomic Energy Agency. The AVRF is constituted from two facilities. The one is the Waste Size Reduction and Storage Facility (WSRSF) which is for reducing waste size, sorting into each material and storing the waste package. The other is the Waste Volume Reduction Facility (WVRF) which is for manufacturing the waste package by volume reducing treatment and stabilizing treatment. WVRF has an induction melting furnace, a plasma melting furnace, an incinerator, and a super compactor for treatment. In this report, we summarized about the basic concept of constructing AVRF, the constitution of facilities, the specifications of machineries and the state of trial operation until March of 2006.

Journal Articles

Trial operation of the advanced volume reduction facilities for LLW at JAEA

Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.

Journal of Nuclear Science and Technology, 44(3), p.441 - 447, 2007/03

 Times Cited Count:9 Percentile:57.83(Nuclear Science & Technology)

The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m$$^{3}$$ and the volume reduction ratio is from 1.7 to 3.7. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005.

Journal Articles

System of the advanced volume reduction facilities for LLW at JAERI

Higuchi, Hidekazu; Momma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

The JAERI constructed the Advanced Volume Reduction Facilities(AVRF). The AVRF consists of the Waste Size Reduction and Storage Facilities(WSRSF) and the Waste Volume Reduction Facilities(WVRF). By operating the AVRF, it will be able to produce waste packages for final disposal and to reduce the amount of the low level solid wastes. Cutting installations for large wastes such as tanks in the WSRSF have been operating since June 1999. The wastes treated so far amount to 600 m$$^{3}$$ and the volume reduction ratio is around 1/3. The waste volume reduction is carried out by a high-compaction process or melting processes in the WVRF. The metal wastes from research reactors are treated by the high-compaction process. The other wastes are treated by the melting processes that enable to estimate radioactivity levels easily by homogenization and get chemical and physical stability. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005.

Journal Articles

Evaluation of core thermal and hydraulic characteristics of HTTR

Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*

Nucl. Eng. Des., 152, p.183 - 196, 1994/00

 Times Cited Count:11 Percentile:70

no abstracts in English

Journal Articles

Evaluation of hot spot factors for thermal and hydraulic design of HTTR

Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*

Journal of Nuclear Science and Technology, 30(11), p.1186 - 1194, 1993/11

 Times Cited Count:7 Percentile:69.12(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Determination of hot spot factors for thermal and hydraulic design of High Temperature Engineering Test Reactor (HTTR)

Maruyama, So; Murakami, Tomoyuki*; Fujii, Sadao*; Fujimoto, Nozomu; Tanaka, Toshiyuki; Sudo, Yukio; Saito, Shinzo

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.425 - 430, 1991/00

no abstracts in English

JAEA Reports

Verification of combined thermal-hydraulic and heat conduction analysis code FLOWNET/TRUMP

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Sudo, Yukio

JAERI-M 88-173, 76 Pages, 1988/09

JAERI-M-88-173.pdf:1.78MB

no abstracts in English

JAEA Reports

Disign and evaluation of core flow distribution in High Temperature Engineering Test Reactor(HTTR)

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Takikawa, Noboru*; *; Sudo, Yukio

JAERI-M 88-154, 147 Pages, 1988/08

JAERI-M-88-154.pdf:2.9MB

no abstracts in English

JAEA Reports

Verification of in-vessel thermal and hydraulic analysis code "FLOWNET"

Maruyama, So; Murakami, Tomoyuki*; Kiso, Yoshihiro*; Sudo, Yukio

JAERI-M 88-138, 39 Pages, 1988/07

JAERI-M-88-138.pdf:1.03MB

no abstracts in English

Oral presentation

Measurement of oxygen concentration of molten metal in the melting treatment for metallic waste, 1; Influence of inside upper volume of melter

Nakashio, Nobuyuki; Osugi, Takeshi; Iseda, Hirokatsu; Sudo, Tomoyuki; Kozawa, Kazushige; Momma, Toshiyuki

no journal, , 

no abstracts in English

Oral presentation

Technical support for planning and installation of simple ground repository; FY2011 status of support activities for promotion of decontamination in the Fukushima Environmental Safety Center, JAEA

Abe, Hironobu; Ikeda, Koki; Mikake, Shinichiro; Nagasaki, Yasushi; Niizato, Tadafumi; Asazuma, Shinichiro; Aoki, Isao; Ishikawa, Nobuyuki; Ishikawa, Hiroyasu; Ishizaki, Nobuhiro; et al.

no journal, , 

no abstracts in English

Oral presentation

JAEA's technical experiences and lessons learned for environmental remediation of Fukushima, 4; Technical supports for local governments

Sudo, Tomoyuki; Ishikawa, Hiroyasu; Uesaka, Takahiro*; Sonoda, Takashi; Ishikawa, Nobuyuki*; Niizato, Tadafumi; Mikake, Shinichiro; Aoki, Isao; Ishizaki, Nobuhiro; Imamura, Hiroaki; et al.

no journal, , 

JAEA is working the decontamination activity for the environmental remediation of Fukushima. In this activity, I support the decontamination activity for local governments to devise a decontamination plan and actually decontaminate. In this report, 1 introduce the technical knowhow for the decontamination activity of a house.

Oral presentation

JAEA's technical experiences and lessons learned for environmental remediation of Fukushima, 2; Technical supports for local governments (decontamination of concrete)

Hata, Katsuro; Ishikawa, Nobuyuki; Uesaka, Takahiro; Sudo, Tomoyuki; Matsumoto, Masaki; Aoki, Isao; Ishizaki, Nobuhiro; Imamura, Hiroaki; Uchida, Shinichi; Kikuchi, Sakae; et al.

no journal, , 

JAEA supports the decontamination activity that the local government of Fukushima carries out. In addition, JAEA carries out instruction and the advice about decontamination. I explain the concrete-based decontamination method of the house which polluted by the accident of the nuclear power plant.

Oral presentation

JAEAs technical experiences and lessons learned for environmental remediation of Fukushima

Aoki, Isao; Asazuma, Shinichiro; Sudo, Tomoyuki; Komiya, Tomokazu; Nakamura, Masahiko; Uchida, Shinichi; Kozawa, Masachiyo; Sonoda, Takashi; Mikake, Shinichiro; Ikeda, Koki; et al.

no journal, , 

JAEAs technical experiences and lessons learned for environmental remediationof Fukushima. (Technical supports for local governments)

Oral presentation

JAEA's technical experiences and lessons learned for environmental remediation of Fukushima technical supports for local governments

Kanazawa, Shingo; Sudo, Tomoyuki; Komiya, Tomokazu; Hata, Katsuro; Nakamura, Masahiko; Kozawa, Masachiyo; Ohata, Kiyoshi; Nanko, Masayuki; Hoshino, Masato; Uchida, Shinichi; et al.

no journal, , 

JAEA is working the decontamination activity for the environmental remediation of Fukushima. In this activity, we support the decontamination activity for local governments to devise actually decontaminate. In this report, we show the decontamination effect of a house.

19 (Records 1-19 displayed on this page)
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