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Journal Articles

Outline of Oarai Waste Reduction Treatment Facility and volume reduction processing

Sakauchi, Hitoshi; Kikuchi, Yuki; Imaizumi, Haruki; Fukui, Yasutaka

Dekomisshoningu Giho, (57), p.34 - 42, 2018/03

OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of radioactive solid waste, which generate from hot facilities in Oarai Research and Development Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. In this report, we describe the outline of OWTF under construction and treatment technologies, in which incinerating and melting.

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.

JAEA Reports

Corroborative tests for Oarai Waste Reduction Treatment Facility using the in-can type high frequency induction heating method

Sakauchi, Hitoshi; Sato, Isamu*; Donomae, Yasushi; Kitamura, Ryoichi

JAEA-Technology 2015-059, 352 Pages, 2016/03

JAEA-Technology-2015-059.pdf:51.53MB

OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of $$alpha$$ solid waste, which was generated from hot facilities in Oarai Research and Develop Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. This report describes corroborative tests, in which incinerating and melting performance for OWTF is confirmed with a full-scale testing furnace. We have been carrying out the tests of incinerating and melting treatment with some kinds of simulated wastes, such as enclosure form of radioactive wastes, material and articles.

Journal Articles

Plasma melting treatment of low level radioactive waste

Nakashio, Nobuyuki; Nakashima, Mikio

Dekomisshoningu Giho, (26), p.45 - 55, 2002/11

Melting treatment of low-level radioactive wastes (LLW) is considered to be a promising technology for the preparation of a stable solid that will be disposed of in near surface repositories. This is because of large reduction of waste volume and production of a stable homogeneous solidified product. In the Japan Atomic Energy Research Institute (JAERI), the construction of the Waste Volume Reduction Facilities (WVRF) has been in progress since 1999. In advance of operation of the WVRF, we have been conducting melting tests of non-metallic solid wastes with the aim of establishing the optimum melting condition for preparation of a stable solid that is suitable for disposal. We have reviewed a part of the melting test conducted in our program.

Journal Articles

Research and development of treatment techniques for LLW from decommissioning; Decontamination and volume reduction techniques

Hirabayashi, Takakuni; Kameo, Yutaka; Nakashio, Nobuyuki

Proceedings of International Symposium on Technologies for the Management of Radioactive Waste from Nuclear Power Plants and Back End Nuclear Fuel Cycle Activities (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Advanced volume reduction of low level radioactive solid waste

Hirabayashi, Takakuni

Energy Hum., 45, p.14 - 18, 1998/06

no abstracts in English

Journal Articles

Volume reduction technologies for low level radioactive waste

Hirabayashi, Takakuni;

Kikai No Kenkyu, 48(5), p.18 - 24, 1996/00

no abstracts in English

JAEA Reports

None

; Kobayashi, Hiroaki; Masaki, Toshio; *; ; ;

PNC-TN8440 94-028, 173 Pages, 1994/06

None

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

Journal Articles

Volume reduction technology for spent resins with catalytic incineration

Yahata, Taneaki

Genshiryoku Kogyo, 39(6), p.21 - 27, 1993/00

no abstracts in English

JAEA Reports

High radioactive $$alpha$$-$$gamma$$ solid Waste treatment facilities Conceptual design study

*; Seki, Sadao*; *

PNC-TJ9409 91-001, 164 Pages, 1991/02

PNC-TJ9409-91-001.pdf:4.41MB

This report describes the result of conceptual design study concerned with "High Radioactive $$alpha$$-$$gamma$$ Solid Waste Treatment Facilities, "which will be planed for the purpose of volume reduction and stabilization of High Radioactive $$alpha$$-$$gamma$$ solid wastes generated and stocked in the O-arai Engineering Center of PNC. In this conceptual design study the basic process of the facilities, which are sufficient to treat each waste and develop technologies, are clarified. This report consist with: (1)Clarification of waste to be treated. (2)Study on the treatment technology and process. (3)Conceptual design of facilities and equipment. (4)Estimation of construction cost and schedule.

Journal Articles

Acid digestion of radioactive combustible wastes; Use of hydrogen peroxide for the acid digestion of ion exchange resins

; ; ;

Journal of Nuclear Science and Technology, 17(11), p.865 - 868, 1980/00

 Times Cited Count:10 Percentile:13.18(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of volume reduction treatment technology for removal soil

Kato, Mitsugu

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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