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Journal Articles

Treatment of electric hydraulic control fluid (EHC Oil) with steam-reforming system

Okadome, Yoshihiro; Aoyama, Yoshio; Sasaki, Yu; Fukushima, Mineo

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

JAEA Reports

Corrosion countermeasure for demonstration scale steam reforming system

Nakanishi, Yoshiki; Aoyama, Yoshio; Nonaka, Kazuharu; Sone, Tomoyuki; Nakazawa, Osamu; Tashiro, Kiyoshi

JAEA-Testing 2011-008, 31 Pages, 2012/03

JAEA-Testing-2011-008.pdf:2.8MB

Steam reforming technology has been developed to reduce the volume of liquid uranium waste such as a Tri-n-butyl phosphate adding n-dodecane solvent (TBP/nDD), which is difficult to incinerate. The localized corrosion like pitting corrosion occurred on the inner surface of the gasification chamber of the demonstration scale steam reforming system during the treatment of TBP/nDD. Therefore we conducted the corrosion tests to identify the form of corrosion. It is found that the form of corrosion is crevice corrosion which caused by the residues generated by treatment of TBP/nDD. The cathodic protection system using a galvanic anode was selected as the corrosion protection method of the gasification chamber. The continuous treatment test of TBP/nDD was conducted using the steam reforming system with the cathodic protection system. As a result, the crevice corrosion did not occur during 600 hours continuous treatment of TBP/nDD, and the effectiveness of the protection method was verified.

Journal Articles

Development of high sensitive and reliable FFD and sodium leak detection technique for fast reactor using RIMS

Ito, Chikara; Araki, Yoshio; Naito, Hiroyuki; Iwata, Yoshihiro; Aoyama, Takafumi

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 12 Pages, 2012/00

no abstracts in English

Journal Articles

Development of passive shutdown system for SFR

Nakanishi, Shigeyuki*; Hosoya, Takusaburo; Kubo, Shigenobu*; Kotake, Shoji; Takamatsu, Misao; Aoyama, Takafumi; Ikarimoto, Iwao*; Kato, Jungo*; Shimakawa, Yoshio*; Harada, Kiyoshi*

Nuclear Technology, 170(1), p.181 - 188, 2010/04

 Times Cited Count:13 Percentile:68.03(Nuclear Science & Technology)

A self-actuated shutdown system (SASS) for sodium cooled fast reactor (SFR) is a passive safety feature which inserts control rods by the gravity force, where the detachment of the rods would be achieved by the coolant temperature rise under anticipated transient without scram (ATWS) conditions. Various out-of-pile tests have already carried out to investigate the basic characteristics of SASS, and a demonstration test of holding stability under the reactor operation condition has been performed, where a function test of the driving system to re-connect and of pulling out the control rod have been done in the experimental reactor JOYO. The element irradiation tests have been also conducted to confirm that no impact will be foreseen by the irradiation. The effectiveness of SASS for a reference core design of JSFR has been evaluated through all types of ATWS. As a result, it is ensured that JSFR will have a reliable passive shutdown system.

JAEA Reports

Thermal treatment for TRU waste sorting

Sasaki, Toshiki; Aoyama, Yoshio; Yamashita, Toshiyuki

JAEA-Technology 2009-001, 33 Pages, 2009/03

JAEA-Technology-2009-001.pdf:2.92MB

A thermal treatment that can automatically unpack TRU waste and remove hazardous materials has been developed to reduce the risk of radiation exposure and save operation cost. The thermal treatment is a process of removing plastic wrapping and hazardous material from TRU waste by heating waste at 500 to 700 $$^{circ}$$C. Plastic wrappings of simulated wastes were removed using a laboratory scale thermal treatment system. Celluloses and isoprene rubbers that must be removed from waste for disposal were pyrolyzed by the treatment. Although the thermal treatment can separate lead and aluminum from the waste, a further technical development is needed to separate lead and aluminum. Future technology development subjects for the TRU waste thermal treatment system are summarized.

Journal Articles

Development of the volume reduction treatment of solid waste system by ultra-high frequency induction furnace

Sakakibara, Tetsuro; Aoyama, Yoshio; Yamaguchi, Hiromi; Sasaki, Naoto*; Nishikawa, Takeshi*; Murata, Minoru*; Park, J.*; Taniguchi, Shoji*; Fujita, Michiru*; Fukuda, Tomoyuki*; et al.

Proceedings of International Waste Management Symposium 2009 (WM '09) (CD-ROM), 15 Pages, 2009/03

The volume reduction treatment of solid waste system by ultra-high frequency induction furnace (UHFIF) was developed from FY2005 to FY2007. Basic data for melting performance were collected by non-radioactive experiments using the bench scale UHFIF with a crucible capacity of 10 liters. Based on the obtained data, engineering specifications were evaluated for a demonstration scale UHFIF with a crucible capacity of 30 liters. A new demonstration scale UHFIF was constructed and melting experiments of surrogate wastes were carried out by this furnace. It was confirmed that the demonstration scale UHFIF can melt ferrous metal, ceramics and aluminum all together and stabilize aluminum by oxidation to alumina. Density, chemical composition, and surface condition of the solidified substances were analyzed, and homogeneity of the solidified substances was confirmed. Melting behavior in the demonstration scale UHFIF was analyzed by computer simulation and simulation results agreed well with the experimental ones. From the design study for a full scale UHFIF with a crucible capacity of 100 liters, basic specifications were evaluated for the full scale UHFIF. Based on the obtained specification, melting behavior in the full scale UHFIF was analyzed by computer simulation.

Journal Articles

Innovative alpha radioactivity monitor for clearance level inspection based on ionized air transport technology; CFD-simulated and experimental ion transport efficiencies for uranium-attached pipes

Hirata, Yosuke*; Nakahara, Katsuhiko*; Sano, Akira*; Sato, Mitsuyoshi*; Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Nambu, Kenichi*; Takahashi, Hiroyuki*; Oda, Akinori*

Journal of Power and Energy Systems (Internet), 2(2), p.561 - 572, 2008/00

Journal Articles

Thermal pretreatment for TRU waste sorting

Sasaki, Toshiki; Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi

Proceedings of International Waste Management Symposium 2008 (WM '08) (CD-ROM), 8 Pages, 2008/00

Japan Atomic Energy Agency conducted a study on thermal treatment of TRU waste to develop a removal technology for materials that are forbidden to dispose of. The thermal pretreatment in which hot nitrogen and/or air is introduced to the waste is a process of removing combustibles, liquids, and low melting point metals from PVC wrapped TRU waste. In this study, thermal pretreatment of simulated waste was conducted using a desktop thermal treatment vessel and a laboratory scale thermal pretreatment system. Combustibles such as papers, PVC, oil, etc. were removed and low melting point metals such as zinc, lead, and aluminum were separated from the simulated waste by the thermal pretreatment.

JAEA Reports

Research and development for treatment and disposal technologies of TRU waste; JFY 2006 annual report

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi*; Sasaki, Ryoichi*; Ichige, Satoru*; et al.

JAEA-Research 2007-067, 130 Pages, 2007/09

JAEA-Research-2007-067.pdf:28.78MB

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology.

Journal Articles

Innovative alpha-radioactivity monitor for clearance level inspection based on ionized air transportation technology, 1; Comparison with mass spectral analysis using uranium-attached samples

Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Sano, Akira*; Naito, Susumu*; Sumida, Akio*; Izumi, Mikio*; Maekawa, Tatsuyuki*; Sato, Mitsuyoshi*; Nambu, Kenichi*; et al.

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04

no abstracts in English

Journal Articles

Innovative alpha radioactivity monitor for clearance level inspection based on ionized air transport technology, 2; CFD-simulated and experimental ion transport efficiencies for uranium-attached pipes

Hirata, Yosuke*; Nakahara, Katsuhiko*; Sano, Akira*; Sato, Mitsuyoshi*; Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Nambu, Kenichi*; Takahashi, Hiroyuki*; Oda, Akinori*

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04

no abstracts in English

Journal Articles

Ion current prediction model considering columnar recombination in alpha radioactivity measurement using ionized air transportation

Naito, Susumu*; Hirata, Yosuke*; Izumi, Mikio*; Sano, Akira*; Miyamoto, Yasuaki; Aoyama, Yoshio; Yamaguchi, Hiromi

Journal of Nuclear Science and Technology, 44(2), p.121 - 128, 2007/02

 Times Cited Count:1 Percentile:11.7(Nuclear Science & Technology)

A reinforced ion current prediction model in the alpha radioactivity measurement using ionized air transportation was presented. Although our previous model explained a qualitative trend of the measured ion current values, their absolute values were considerably overestimated. In order to explain them quantitatively, the model was reinforced in consideration of columnar recombination. It was found that our new model explains the considerable ion loss in the initial stage of ion diffusion and narrows the gap between the predicted and measured ion current values. This model also indicated a prospective suppression of ion loss due to columnar recombination by spraying a high-speed air flow on the contaminated surface. This suppression was experimentally investigated and confirmed. In conclusion, the theoretical relationship between alpha radioactivity and ion current was clarified quantitatively in laminar flow and turbulent pipe flow.

JAEA Reports

Experimental investigation of melting treatment of nonflammable solid wastes in a canister with a high-frequency induction furnace

Ozawa, Tatsuya; Miyamoto, Yasuaki; Suto, Makoto; Aoyama, Yoshio; Yamaguchi, Hiromi

JAEA-Technology 2006-050, 88 Pages, 2006/11

JAEA-Technology-2006-050.pdf:14.49MB

Melting treatment is one of the volume reduction processes for nonflammable radioactive solid wastes. Though it is applied to the volume reduction process for the low-level radioactive wastes generated at nuclear power plants, it still has technical problems to be solved. The results of our previous investigation of existing melting treatment facilities and conceptual design of the melting treatment system for transuranic waste, made these technical problems clear. To solve them, we have been carrying out the experiments of melting treatment of the simulated transuranic wastes which are nonflammable solid wastes. This report describes the progress in investigating these problems, as well as the results of recent experiments.

Journal Articles

None

Aoyama, Takafumi; Torimaru, Tadahiko; ; Arii, Yoshio;

Nihon Genshiryoku Gakkai-Shi, 41(9), p.946 - 953, 1999/00

 Times Cited Count:1 Percentile:13.4(Nuclear Science & Technology)

None

Journal Articles

Core and Fuel Management Experience of the JOYO Irradiation Core (the MK-II Core)

Arii, Yoshio; Aoyama, Takafumi; Suzuki, Soju

Nihon Genshiryoku Gakkai-Shi, 39(4), p.315 - 325, 1997/00

 Times Cited Count:4 Percentile:37.89(Nuclear Science & Technology)

None

Journal Articles

Code and Fuel Management Experience of the JOYO Irradiation Core (MK-III Core)

Arii, Yoshio; ; Aoyama, Takafumi; Suzuki, Soju

Proceedings of International Conference on the Physics of Reactors (PHYSOR '96), 0 Pages, 1996/00

None

Journal Articles

None

; Arii, Yoshio; Aoyama, Takafumi; Suzuki, Soju

Vol.3 I-p28, , 

None

Oral presentation

Alpha radioactivity measurement based on ionized air transportation technology, 13; Influence evaluation of background drift

Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Izumi, Mikio*; Naito, Susumu*; Yamamoto, Shuji*; Sano, Akira*; Nambu, Kenichi*; Takahashi, Hiroyuki*; Oda, Akinori*

no journal, , 

no abstracts in English

Oral presentation

Alpha radioactivity measurement based on ionized air transportation technology, 16; Verification test with uranium samples

Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Sano, Akira*; Naito, Susumu*; Sumida, Akio*; Sato, Mitsuyoshi*; Nambu, Kenichi*; Takahashi, Hiroyuki*; Oda, Akinori*

no journal, , 

no abstracts in English

Oral presentation

Alpha radioactivity measurement based on ionized air transportation technology, 18; Verification of a suppression method of ion loss by ion-ion recombination by air splaying

Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Naito, Susumu*; Sano, Akira*; Hirata, Yosuke*; Noda, Etsuo*; Sato, Mitsuyoshi*; Nambu, Kenichi*; Takahashi, Hiroyuki*; et al.

no journal, , 

no abstracts in English

58 (Records 1-20 displayed on this page)