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Oral presentation

Development of PRW technology for ODS steel, 12; Strength evaluation test by using artificially-defected test pieces

Seki, Masayuki; Kihara, Yoshiyuki; Hirako, Kazuhito*; Motoki, Kazuhiko*; Tsukada, Tatsuya*

no journal, , 

no abstracts in English

Oral presentation

On performance experience and measurements with Ningyo Waste Assay System (NWAS)

Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi

no journal, , 

We developed uranium mass assay systems for 200-litter wastes drums applied neutron and $$gamma$$ measurements by NDA method. In this intermediate report we will describe measurement systems and trial data. The systems are composed of the 16 pieces of helium-3 proportional counters for neutron detection and a large sized NaI(Tl) scintillation detector for $$gamma$$-ray detection. The extensive testing trials using the calibrated uranium sources with different enrichment and some kinds of matrices in drums were performed. Through the one year testing the useful experiences of this system concerning neutron and $$gamma$$-ray measurements for uranium mass were obtained. Almost all instruments and software were so good performance as is designed. As the next step we are going to schedule to try measurements for actual wastes that are stored in the Uranium Refining and Conversion Plant at Ningyo-toge, and put practical uses near future. Our research was accomplished with the support of Los Alamos National Laboratory.

Oral presentation

Feasibility study on material creation and new-type fuel utilization by using HTTR, 1; Outline of feasibility study

Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*

no journal, , 

As collaborative research project by Japan Atomic Energy Agency, Toyota Tsusho Corporation and Nuclear Fuel Industries, Ltd., new utilizations of HTGR and new R&D of a cooperative relationship between car industries and HTGR are presented. Specifically, we showed the results of feasibility study on material creation and new-type fuel utilization by using HTTR.

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

Replacement of filter casing in the vessel ventilation of HAW storage process at the Tokai reprocessing plant

Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Decommissioning Project of Uranium Conversion Plant, 1; Decommissioning result (The First half of F.Y. 2010)

Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake

no journal, , 

no abstracts in English

Oral presentation

Status of development of a 500 kV photo-cathode electron gun for the next generation ERL light sources

Nishimori, Nobuyuki; Nagai, Ryoji; Hajima, Ryoichi; Yamamoto, Masahiro*; Miyajima, Tsukasa*; Honda, Yosuke*; Kuriki, Masao*; Iijima, Hokuto*; Kuwahara, Makoto*; Okumi, Shoji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Numerical analysis of large pipe break in PHTS using the Monju system startup tests data

Yamada, Fumiaki; Araki, Kosuke*

no journal, , 

There was not the influence that Monju system startup tests data gave to numerical analysis of large pipe break in primary heat transfer system concerned from comparison actual plant base analysis and before conservative base analysis.

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

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

Improvement of unloading pool crane at TRP

Takeyasu, Shinji; Takebayashi, Hiroyuki; Watanabe, Kazunori*; Shimizu, Takenori

no journal, , 

no abstracts in English

Oral presentation

Magnetic emittance correction by a backing-coil for a photo-cathode electron gun

Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki

no journal, , 

no abstracts in English

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)