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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

Status of theoretical investigation of surrogate reactions

Chiba, Satoshi; Ogata, Kazuyuki*; Hashimoto, Shintaro; Aritomo, Yoshihiro

no journal, , 

no abstracts in English

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

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

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)