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Oral presentation

Verification tests for clearance monitor at Fugen Decommissioning Engineering Center

Kawagoe, Shinji; Higashiura, Norikazu; Goto, Tetsuo*

no journal, , 

no abstracts in English

Oral presentation

Investigation of $$^{99}$$Mo amount generated by irradiating natural Mo in JRR-3

Komeda, Masao; Hirose, Akira; Sorita, Takami; Wada, Shigeru; Ishikawa, Koji*

no journal, , 

no abstracts in English

Oral presentation

Basic study on decontamination of TRU wastes with cerium mediated electrolytic oxidation method

Ishii, Junichi; Kobayashi, Fuyumi; Uchida, Shoji; Sumiya, Masato; Umeda, Miki

no journal, , 

no abstracts in English

Oral presentation

Study on hydrogenation and radiation effects in Zr-Nb alloys; Development of an interatomic potential for Zr-H binary systems

Udagawa, Yutaka; Yamaguchi, Masatake; Abe, Hiroaki*; Sekimura, Naoto*

no journal, , 

no abstracts in English

Oral presentation

Basic study on system decontamination by iodine heptafluoride, 1; Estimation of deposition rate and mechanism based uranium enrichment plant operation data

Yokoyama, Kaoru; Hata, Haruhi; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*

no journal, , 

The decontamination technique using the iodine heptafluoride is known as a system decontamination technique of facilities like the uranium enrichment plant where the uranium hexafluoride was handled. In this report, the mechanism of the system decontamination using the iodine heptafluoride is clarified at a molecular level. The generation process of the uranium tetrafluoride is estimated using the plant operation data. In addition, the generation speed of the uranium tetrafluoride and the activation energy are of the uranium tetrafluoride and iodine heptafluoride reaction are estimated.

Oral presentation

Development of manufacturing technology for a large amount of $$^{99m}$$Tc generated from natural-Mo(n,$$gamma$$)$$^{99}$$Mo, 4; Analysis in the verification test of the producing process of $$^{99m}$$Tc milked from a highly radioactive $$^{99}$$Mo

Sonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of pyro-chemical reprocessing technology using alkaline molybdate melt, 7; Measuring UO$$_{2}$$$$^{2+}$$/UO$$_{2}$$$$^{+}$$ redox potential in Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$ by absorption spectrometry

Nagai, Takayuki; Fukushima, Mineo; Myochin, Munetaka; Uehara, Akihiro*; Fujii, Toshiyuki*; Yamana, Hajimu*

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 9; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*

no journal, , 

This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 7; Estimation of the amount of Pu in dissolution residue formed at highly concentrated condition

Ikeuchi, Hirotomo; Shibata, Atsuhiro; Ouchi, Shinichi; Katsurai, Kiyomichi; Sano, Yuichi; Washiya, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Development of metal pyro-processing, 11; Development of actinide recovery process from residue of pyro-processing

Kitawaki, Shinichi; Nakayoshi, Akira; Sakamura, Yoshiharu*; Akiyama, Naoyuki*

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 8; Effect of rocking motion on mass transfer in rotary dram type continuous dissolver

Hoshino, Takanori; Ikeuchi, Hirotomo; Sano, Yuichi; Watanabe, Masayuki; Suganuma, Takashi

no journal, , 

no abstracts in English

Oral presentation

Development of metal pyro-processing, 10; Anodic behavior of U-Pu-Zr alloy fuel in electrorefining process

Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Akiyama, Naoyuki*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

no abstracts in English

Oral presentation

Basic study on system decontamination by iodine heptafluoride, 2; Formulate of potential model for deposition mechanism of uranium compound

Hata, Haruhi; Yokoyama, Kaoru; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*

no journal, , 

As a first step to elucidate the molecular mechanism of decontamination systems for iodine heptafluoride, uranium hexafluoride and the metal (iron), the possibility of physical adsorption and chemical reactions with uranium hexafluoride and uranium tetrafluoride (solid), we investigate the possibility of physical adsorption and chemical reactions of this. Therefore, the intermolecular of uranium hexafluorides, iron and uranium hexafluoride, uranium tetrafluoride and uranium hexafluoride (solid) and evaluated by molecular orbital method to the intermolecular potential between, based on this data, MD law adhesion mechanism was estimated by uranium hexafluoride.

Oral presentation

Development of high-resolution atmospheric dispersion models in SPEEDI-MP; Turbulent flow and plume dispersion within a building array

Nakayama, Hiromasa; Nagai, Haruyasu

no journal, , 

We perform Large-Eddy Simulations (LES) on turbulent flows and plume dispersions within and over regular arrays of cubic buildings with various roughness densities and investigate the influence of the building arrangement pattern on the characteristics of mean and fluctuation concentrations for the assessment of human health hazard from toxic substances and the safety analysis of flammable gas.

Oral presentation

Maintenance management of valves in low level radioactive effluent treatment process at TRP

Komoto, Norio; Sasaki, Hirofumi; Kawata, Tsuyoshi; Taki, Kiyotaka; Kinoshita, Shigemi*

no journal, , 

no abstracts in English

Oral presentation

System startup test of Monju (Core confirmation test); Characterization evaluation of ultrasonic sodium thermometer

Okusa, Kyoichi; Muranaka, Makoto; Sotsu, Masutake; Kimura, Koichi

no journal, , 

The ultrasonic thermometer is installed on the piping of the secondary cooling system in Monju. The characteristic of the ultrasonic thermometer in case of the sodium temperature change was evaluated as the first stage of system startup test of Monju. The evaluated temperature by the ultrasonic thermometer agreed well with the thermocouple measurement in this condition.

Oral presentation

Reactor physics on STACY heterogeneous core with light water moderator, 3; Evaluation of kinetics in reactivity insertion events

Aoyama, Yasuo; Komuro, Michiyasu; Seki, Masakazu; Izawa, Kazuhiko; Sono, Hiroki; Ogawa, Kazuhiko; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Mizunami Underground Research Laboratory Project, 1; Status of construction and research & development

Sato, Toshinori; Saegusa, Hiromitsu; Hama, Katsuhiro; Ogata, Nobuhisa; Mikake, Shinichiro

no journal, , 

Japan Atomic Energy Agency has been conducting Mizunami Underground Research Laboratory (URL) Project aiming to establish a firm scientific basis for safe geological disposal including: establishing investigation techniques, analysis and assessment of the deep geological environment, and applicability assessment of engineering technologies for designing and constructing underground facilities. This report describes the construction status of the URL, the results of deep geological investigations carried out, and the future plan of this project.

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi; Terai, Takayuki*; et al.

no journal, , 

Three and half years has been passed from the start of IFMIF/EVEDA. In IFMIF/EVEDA, tasks for Lithium Target System consists of 5 validation tasks (LF1-5) and a design task (ED3), and are shared by Japan and Europe. Japan is covering the construction and operation of EVEDA Li Test Loop (LF1), diagnostics (LF2), purification system (LF4), remote handling system (LF5) and engineering design (ED3) with the contribution from universities. The present status of these tasks will be reported in the conference.

Oral presentation

Development of a granulator for MOX fuel fabrication for FBR

Suzuki, Mitsuru

no journal, , 

no abstracts in English

267 (Records 1-20 displayed on this page)