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Kozai, Naofumi; Sato, Junya; Osugi, Takeshi; Shimoyama, Iwao; Sekine, Yurina; Sakamoto, Fuminori; Onuki, Toshihiko
Journal of Hazardous Materials, 416, p.125965_1 - 125965_9, 2021/08
Times Cited Count：24 Percentile：86.19(Engineering, Environmental)Fujii, Kengo*; Ochi, Kotaro; Obuchi, Atsushi*; Koike, Yuya*
Journal of Environmental Management, 217, p.157 - 163, 2018/07
Times Cited Count：35 Percentile：77.62(Environmental Sciences)After the Fukushima Daiichi-Nuclear Power Plant accident, environmental recovery was a major issue because a considerable amount of municipal solid waste incineration (MSWI) fly ash was highly contaminated with radioactive cesium. In this study, MSWI fly ash was sampled in Fukushima Prefecture, and the physicochemical properties of radioactive cesium in MSWI fly ash were evaluated by particle size classification and the Japanese leaching test No. 13 (JLT-13). The results obtained from the classification of fly ash indicated that the activity concentration of radioactive cesium and the content of the coexisting matter (i.e., chloride, potassium, and sylvite) temporarily change in response to the particle size of fly ash. X-ray diffraction results indicated that water-soluble radioactive cesium exists as CsCl because of the cooling process and that insoluble cesium is bound to the inner sphere of amorphous matter.
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.
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 
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.
Nakayama, Takuya; Kawato, Yoshimi; Osugi, Takeshi; Shimazaki, Takejiro; Hanada, Keiji; Suzuki, Shinji; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro
JAEA-Technology 2014-046, 56 Pages, 2015/03
JAEA-Technology-2014-046.pdf:7.61MB
The combustible and flame-retardant radioactive wastes generated as a result of the research activities in Japan Atomic Energy Agency (JAEA) are incinerating to reduce their volume. The incinerated ash is planned to be solidified using cement for disposal. Since the properties of ashes generated in each institute of JAEA are varied with the type of incinerator and the wastes to be incinerated, it is necessary to do fundamental solidification tests in each institute to decide operating conditions of the planning cement solidification facility. It is important to standardize evaluating methods of cement and solidified waste because some characters depend on measuring method. This user's guide have been prepared how to decide the cement solidifying conditions of ash to design the cement solidification facility in JAEA. Requirements on the regulations of solidified radioactive waste have been examined and seven technical criteria, e.g. compressive strength, fluidity, have been selected as characters to be evaluated. Some empirical notes about selection of cement, admixtures, procedure on making a test piece, evaluation of expanding, compressive strength, solubility have been described. The strategy of tests and tips for finding optimized solidification condition has been summarized. Finally the example of optimized conditions satisfied the requirements and some problems to be solved have been described.
Kozai, Naofumi; Suzuki, Shinichi; Aoyagi, Noboru; Sakamoto, Fuminori; Onuki, Toshihiko
Water Research, 68, p.616 - 626, 2015/01
Times Cited Count：20 Percentile：62(Engineering, Environmental)The radioactive fallout cesium (
Cs) in the sewage sludge ashes (SSAs) produced after the Fukushima Daiichi Nuclear Accident was tested. Two of tested five SSAs contained Cs above the radioactivity criterion for controlled landfill disposal in Japan. The minerals of SSAs are divided into two groups: an HCl-soluble phase mainly composed of phosphates and metal oxides; and silicates. The majority of Cs was contained in the HCl-soluble phase. Among the HCl-soluble subphases, Fe-bearing phases, probably iron oxides, were mainly responsible for Cs retention. Pre-pulverizing SSAs and heating them in an aqueous HCl was the most effective method of dissolving the HCl-soluble phase. The radioactivity concentrations of Cs in all the HCl-treatment residues were below the criterion. This residue was mostly composed of silicates. Static leaching tests of the residue revealed that Cs is very stably immobilized in the silicates.
Tamada, Masao
Kankyo Shigen Kogaku, 51(2), p.99 - 101, 2004/04
Fibrous chelate adsorbents have been synthesized by radiation-induced graft polymerization onto polyethylene nonwoven fabric. Graft polymerization was induced by electron beam irradiation to the trunk polymer. Then, irradiated trunk polymer was contacted with reactive monomer having function of chelate agent or its precursor. The precursor was chemically converted to chelate agent. The resulting fibrous chelate adsorbent gave the high space velocity more than 500 h
in removal of lead from its solution. Such adsorbent was applied to the removal of cadmium from scallop processing waste and the removal of lead from the contaminated water which was produced by washing the inside of incinerator.
Hoshi, Akiko; Nakashio, Nobuyuki; Nakashima, Mikio
Genshiryoku Bakkuendo Kenkyu, 10(1-2), p.93 - 102, 2004/03
The Japan Atomic Energy Research Institute (JAERI) decided to adopt an advanced volume reduction program for low-level radioactive wastes. In this program, inorganic wastes are converted to stable glassy products suitable for disposal by a plasma melting system in the Waste Volume Reduction Facilities (WVRF). In this paper, plasma melting test of crucibles,ceramic filter elements,asbestos,and simulated fly ashes were carried out as a part of technical support for WVRF. The plasma melting treatment was applicable for crucibles and asbestos because homogeneous and glassy products were obtained by controlling of waste and loading condition. It was found that an oxidizing slag is needed for effective melting condition of ceramic filter elements with a plasma torch with inert gas, and controlling of slag components have the potential to stabilize volatile metals such as Zn, Pb in a solidified product in the melting test of simulated fly ash.
Hirota, Koichi
Isotope News, (566), p.9 - 11, 2001/07
Japan Atomic Energy Research Institute has started the research on Electron-beam technology for decomposing more than 90 % of PCDD/D from MSWI in October of 2000. This test facility is operated till March of 2002. Then, this technology will be transferred to private companies after the feasibility study is completed.
Ishiyama, Takashi; Bamba, Tsunetaka; Mitamura, Hisayoshi; Maeda, Toshikatsu
Haikibutsu Gakkai Rombunshi, 12(2), p.82 - 86, 2001/03
no abstracts in English
Hashimoto, Shoji
Hoshasen To Sangyo, (89), p.47 - 49, 2001/01
no abstracts in English
Iwase, Masanori*
JNC TJ8400 2000-063, 78 Pages, 2000/03
JNC-TJ8400-2000-063.pdf:1.93MB
This study is aimed at controlling oxidation reaction of molten metal by ash in incineration systems, and at positively utilizing the oxidation reaction for decontamination of slag. In this year, in order to investigate physico-chemical properties of mixed fused salt containing alkali sulfates, with special focus on the behaviour of oxygen anion in the melts, Cu
/ Cu
redox equilibrium experiments were carried out. Among the effect of various parameters on Cu / Cu ratio in binary and ternary alkali sulfate melts, the effect of partial pressures of oxygen and SO
was mainly investigated in the study. Variation in Cu / Cu ratio were presented as the function of partial pressures of oxygen and SO, respectively. Possible thermodynamic interpretation were made on the experimental results. In addition, the dissolution of CrO
in mixed alkali sulfates were also investigated as a first step to elucidate the mechanism of hot corrosion. With this investigation, an important finding was obtained that the solubility of CrO for melts with same average ionic radius, in other words, oxygen ion activity, were essentially identical under constant temperature and atmosphere.
; ; 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 -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
C for the combustible waste, 1300C for the ion exchange resin, 1500C for the noncombustible waste. (b)Air flow is 90Nm
/h. Air temperature is 300C. 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
or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO
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 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 ...
Okoshi, Minoru
Kemikaru Enjiniyaringu, 44(2), p.60 - 64, 1999/02
no abstracts in English
; Takahashi, Hideki
Dekomisshoningu Giho, 0(14), p.73 - 81, 1996/08
no abstracts in English
solid waste incrinerator;
Dekomisshoningu Giho, (8), p.22 - 30, 1993/06
no abstracts in English
Kihara, Shinji; Yahata, Taneaki; ; Nishimura, Mitsuhiro
Incineration Conf. Proc., p.457 - 460, 1993/00
no abstracts in English
