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JAEA Reports

Safety measures in the melting facilities of The Advanced Volume Reduction Facilities; Document collection of discussion meetings related to melting facilities

Iketani, Shotaro; Yokobori, Tomohiko; Ishikawa, Joji; Yasuhara, Toshiyuki*; Kozawa, Toshiyuki*; Takaizumi, Hirohide*; Momma, Takeshi*; Kurosawa, Shingo*; Iseda, Hirokatsu; Kishimoto, Katsumi; et al.

JAEA-Review 2018-016, 46 Pages, 2018/12

JAEA-Review-2018-016.pdf:12.79MB

Japan Atomic Energy Agency (JAEA) adopts melting process for the waste processing and packaging method of radioactive miscellaneous solid waste in NSRI because melting process is effective in radioactivity evaluation, volume reduction, and stabilization treatment. Metal melting processing facilities, Incinerator, and Nonmetal melting processing facilities (hereinafter referred to as melting process facilities) have taken lots of safety measures, including measures for preventing the recurrence of the fire accidents. To exchange opinions and discuss the validity of these measures and so on with internal personnel and external experts, "Discussions on Melting Process Facilities" was held. As a document collection, this paper summarizes presentation materials of discussion meetings. Presentation materials describe "Outline of AVRF", "Safety measures in the melting facilities in WVRF", "Operation management of the melting facilities in WVRF", "Comparison of the past accident cases between facilities in and outside Japan and WVRF", and "Introduction of past accident cases and safety measures in other facilities from each committee".

Journal Articles

Chemical stability of solidified products made from incombustible wastes by plasma melting

Kameo, Yutaka; Haraga, Tomoko; Nakashio, Nobuyuki; Hoshi, Akiko; Nakashima, Mikio

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.354 - 362, 2004/12

In order to investigate chemical stability of solidified products made from Low Level Radioactive Wastes (LLW) by plasma melting, a leaching test based on the MCC (Material Characterization Center)-3S Agitated Powder Leach Test Method was performed to determine Normalized Elemental Mass Loss (NL$$_{i}$$) of both main components (Na, Al, Si, Ca, and Fe) of the solidified product and radioactive tracers ($$^{60}$$Co, $$^{137}$$Cs, and $$^{152}$$Eu) incorporated into it. The results of leaching test indicated that NLi value was greatly affected by basicity defined as weight ratio of CaO to SiO$$_{2}$$ in the solidified product, while effect of FeO concentration on NL$$_{i}$$ value was small. In the case of basicity less than 0.8, logarithm of NL$$_{i}$$ linearly increased with the basicity, implying that NL$$_{i}$$ value can be estimated by chemical composition of the solidified products.

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

Characterization of solidified products yielded by plasma melting treatment of simulated non-metallic radioactive wastes

Nakashima, Mikio; Fukui, Toshiki*; Nakashio, Nobuyuki; Isobe, Motoyasu*; Otake, Atsushi*; Wakui, Takuji*; Hirabayashi, Takakuni*

Journal of Nuclear Science and Technology, 39(6), p.687 - 694, 2002/06

 Times Cited Count:16 Percentile:69.83(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study on the barrier performance of molten solidified waste, 1; Review of the performance assessment research

Maeda, Toshikatsu; Sakamoto, Yoshiaki; Nakayama, Shinichi; Yamaguchi, Tetsuji; Ogawa, Hiromichi

JAERI-Review 2001-001, 25 Pages, 2001/02

JAERI-Review-2001-001.pdf:1.28MB

no abstracts in English

JAEA Reports

Study on melting coditions of radioactive miscellaneous solid waste (Contract research)

Fukui, Toshiki; Nakashio, Nobuyuki; Isobe, Motoyasu; Otake, Atsushi*; Wakui, Takuji*; Hirabayashi, Takakuni*; Nakashima, Mikio

JAERI-Review 2000-033, 82 Pages, 2001/02

JAERI-Review-2000-033.pdf:2.61MB

no abstracts in English

Journal Articles

Study on plasma melting of miscellaneous low-level radioactive waste

Nakashio, Nobuyuki; Wakui, Takuji*; Otake, Atsushi*; Nakashima, Mikio; Fukui, Toshiki*; Isobe, Motoyasu*

Proceedings of 8th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01) (CD-ROM), 4 Pages, 2001/00

no abstracts in English

JAEA Reports

Tests on decisive proof for the incinerating and melting facility using the in-can type high frequency induction heating

; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2000-002, 149 Pages, 1999/12

JNC-TN9410-2000-002.pdf:23.51MB

LEDF (Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose $$alpha$$-waste configured with combustible waste, pvc & rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. (1)Processing speed is 6.7kg/h for the combustible waste, 13.0kg/h for the ion exchange resin, and 30.0kg/h for the noncombustible waste. For above optimum processing conditions are as follows. (a)Operating temperature is 1000$$^{circ}$$C for the combustible waste, 1300$$^{circ}$$C for the ion exchange resin, 1500$$^{circ}$$C for the noncombustible waste. (b)Air flow is 90Nm$$^{3}$$/h. Air temperature is 300$$^{circ}$$C. Air velocity is 20m/s. (2)Incineration time per day is 5h. Warm-up time and incineration time from the stop of waste charging is 0.5h. Melting time per day is 5h inconsideration of heating hold time of incinerated ash and melting of quartz. Warm-up time is 0.5h. (3)The system decontamination factor in Co, Cs and Ce with pilot testing equipment is 10$$^{5}$$ or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO$$_{4}$$ gas absorber is as follows. (a)Its diameter distribute in the range of 0.8-1.7mm. (b)To have a decontamination factor of 10$$^{3}$$ can achieve for retention time of 3 seconds and its life time is about 1 year. (5)In terms of the distribution of the nuclear species in molten solid is evenly distributed. It was also confirmed that the distribution of main elements in ceramic layer is ...

JAEA Reports

Pyrolysis and Melt Solidification Test of $$beta$$$$gamma$$ Solid Wastes by Microwave Heating

; *; ; ; ; ; *; *

JAERI-M 84-001, 76 Pages, 1984/02

JAERI-M-84-001.pdf:3.16MB

no abstracts in English

Oral presentation

Characterization of fuel debris (27'A), 5; Phase evaluation of simulated debris prepared by melting (U, Pu, Zr)O$$_{2}$$ with iron

Akashi, Masatoshi; Morimoto, Kyoichi; Kato, Masato

no journal, , 

no abstracts in English

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