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JAEA Reports

Mizunami Underground Research Laboratory Project; Compilation of results of geological investigation at the shafts and research galleries from the depth of 300m to 500m

Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki; Tsuruta, Tadahiko; Sasao, Eiji; Ikeda, Koki; Mikake, Shinichiro; Hara, Ikuo; Yamamoto, Masaru

JAEA-Data/Code 2012-025, 32 Pages, 2013/01

JAEA-Data-Code-2012-025.pdf:3.03MB
JAEA-Data-Code-2012-025-appendix.zip:126.32MB

This document presents the data of geological investigations in the shafts and research galleries from the depth of 300m to 500m of the MIU from the 2008 fiscal year to the 2011 fiscal year. In the shafts and research galleries of the MIU, although the Cretaceous Toki granite is distributed, pegmatite, aplite and lampropyre dike are distributed partially.

Journal Articles

Combustion characteristics of generating hydrogen during sodium-concrete reaction

Seino, Hiroshi; Ohno, Shuji; Yamamoto, Ikuo*; Miyahara, Shinya

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 10 Pages, 2012/12

A hydrogen combustion experiment was conducted to simulate the sodium-concrete reaction under oxygen-existing conditions. As a result, it was found that hydrogen was burnt at the sodium pool surface because as sodium combustion heat played a role of the ignition energy, and the hydrogen combination ratio increased with the increase of the oxygen concentration in the atmosphere.

JAEA Reports

Mizunami Underground Research Laboratory Project, Compilation of results of geological investigation at the shafts and research galleries

Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki; Tsuruta, Tadahiko; Sasao, Eiji; Ikeda, Koki; Mikake, Shinichiro; Hara, Ikuo; Yamamoto, Masaru

JAEA-Data/Code 2012-009, 47 Pages, 2012/07

JAEA-Data-Code-2012-009.pdf:3.7MB
JAEA-Data-Code-2012-009-appendix(DVD-ROM)-1.zip:236.07MB
JAEA-Data-Code-2012-009-appendix(DVD-ROM)-2.zip:615.87MB
JAEA-Data-Code-2012-009-appendix(DVD-ROM)-3.zip:45.88MB
JAEA-Data-Code-2012-009-appendix(DVD-ROM)-4.zip:115.54MB
JAEA-Data-Code-2012-009-appendix(DVD-ROM)-5.zip:230.55MB

This document presents the data of geological investigations in the shafts and research galleries to the depth of 300 m of the MIU from the 2004 fiscal year to the 2008 fiscal year. In the shafts and research galleries of the MIU, the Cretaceous Toki granite is unconformably overlain by the generally flat lying Miocene Mizunami Group (younging upwards from the Toki Lignite-bearing Formation to the Hongo and Akeyo Formations) with a depth of about 166 m to 168 m.

JAEA Reports

Mizunami Underground Research Laboratory Project; Compilation of results of the borehole investigation at research galleries and shaft

Ueno, Takashi; Tokuyasu, Shingo; Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki; Tsuruta, Tadahiko; Sasao, Eiji; Ikeda, Koki; Mikake, Shinichiro; Hara, Ikuo; et al.

JAEA-Data/Code 2012-008, 136 Pages, 2012/07

JAEA-Data-Code-2012-008.pdf:27.39MB
JAEA-Data-Code-2012-008(errata).pdf:1.55MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-1.zip:790.9MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-2.zip:834.48MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-3.zip:533.98MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-4.zip:712.56MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-5.zip:525.5MB

This report compiles data of results from borehole investigations which has been carried out research gallery of Mizunami Underground Research Laboratory (MIU) in the fiscal year from 2005 to 2011. These data include results of core observation, geophysical logging, and so on.

Journal Articles

Evaluation method of thermal deformation for Fast Spectrum Light Water Reactor (FLWR)

Ishijima, Yasuhiro; Ioka, Ikuo; Kiuchi, Kiyoshi; Kaneko, Tetsuji*; Okubo, Tsutomu; Yamamoto, Masahiro

Atsuryoku Gijutsu, 47(1), p.12 - 17, 2009/01

We investigate one of these innovative water reactors; Fast Spectrum Light Water Reactor (FLWR). It has unique construction for the reactor core but the fuel cladding material will be exposed in high internal pressure and axial load and complex temperature distribution. Therefore, we conducted a specially designed fatigue-creep test that were simulated several parameters (thermal distribution, temperature variation, internal pressure variation and binding stress) to evaluate an applicability of fuel cladding material for FLWR. Zircalloy-2, which is common cladding material, was used for the test. Test result was confirmed to compare the deformation value between tested and calculated. The result showed the evaluation method could be controlled several parameters simultaneously and the deformation value after the test coincided to the calculated value. This method is sufficient to evaluate thermal deformation characteristics for FLWR.

Journal Articles

Current status of the control system for J-PARC accelerator complex

Yoshikawa, Hiroshi; Sakaki, Hironao; Sako, Hiroyuki; Takahashi, Hiroki; Shen, G.; Kato, Yuko; Ito, Yuichi; Ikeda, Hiroshi*; Ishiyama, Tatsuya*; Tsuchiya, Hitoshi*; et al.

Proceedings of International Conference on Accelerator and Large Experimental Physics Control Systems (ICALEPCS '07) (CD-ROM), p.62 - 64, 2007/10

J-PARC is a large scale facility of the proton accelerators for the multi-purpose of scientific researches in Japan. This facility consists of three accelerators and three experimental stations. Now, J-PARC is under construction, and LINAC is operated for one year, 3GeV synchrotron has just started the commissioning in this October the 1st. The completion of this facility will be next summer. The control system of accelerators established fundamental performance for the initial commissioning. The most important requirement to the control system of this facility is to minimize the activation of accelerator devices. In this paper, we show that the performances of each layer of this control system have been achieved in the initial stage.

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Oral presentation

Development of CONTAIN/LMR code for LMFBR's ex-vessel phenomena; Improvement and validation of sodium-concrete reaction model

Seino, Hiroshi; Ohno, Shuji; Miyahara, Shinya; Izumi, Keitaro*; Yamamoto, Ikuo*

no journal, , 

We conducted a validation calculation in order to mainly confirm alumina-related reactions considered in the sodium-concrete reaction model in the CONTAIN/LMR code. As a result, it was found that though there were some problems in quantitative evaluation, CONTAIN/LMR could simulate the characteristics of these reactions.

Oral presentation

Development of U and Pu co-processing process; The Result of U and Pu co-processing process test by miniture mixser-settlers with internal recycle in the case of Pu/U:1% in feed solution)

Fujimoto, Ikuo; Yanagibashi, Futoshi; Yamamoto, Kohei; Sato, Takehiko; Obu, Tomoyuki; Taki, Kiyotaka

no journal, , 

no abstracts in English

Oral presentation

Development of U and Pu co-recovery process (co-processing) for future reprocessing

Yamamoto, Kohei; Yanagibashi, Futoshi; Fujimoto, Ikuo; Sato, Takehiko; Obu, Tomoyuki; Taki, Kiyotaka; Hayashi, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 3; Corium/sodium-concrete interaction behavior

Kawaguchi, Munemichi; Uno, Masayoshi*; Konishi, Kensuke; Yamamoto, Ikuo*; Miyahara, Shinya*

no journal, , 

We started a project on "Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor" as a program for R&D for nuclear system, development of basic technology for safety. We planed to develop an evaluation method based on experiments of hydrogen generation and concrete ablation in sodium-concrete reaction. This report shows the plan and a part of the sodium test.

Oral presentation

Multifunctional optical probe for the investigation in radiation harsh conditions

Nishimura, Akihiko; Furuyama, Takehiro*; Ito, Fuyumi*; Ito, Chikara; Naito, Hiroyuki; Oba, Hironori; Yamamoto, Shunya; Wakaida, Ikuo; Sugiyama, Akira

no journal, , 

no abstracts in English

Oral presentation

Development of remote $$gamma$$-ray measurement technique under high radiation dose using ruby scintillator and optical fiber

Ito, Chikara; Yamamoto, Takahiro; Sekine, Takashi; Wakaida, Ikuo; Miyazaki, Nobuyuki*

no journal, , 

no abstracts in English

Oral presentation

Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 8; Estimation of phase equilibrium state of fuel debris under sodium by thermodynamic calculation

Yamamoto, Ikuo*; Uno, Masayoshi*; Miyahara, Shinya; Kawaguchi, Munemichi

no journal, , 

An estimation technology and reaction model on phase equilibrium state of fuel debris under sodium using thermodynamics calculation has been developed. In this study, the reaction products were calculated in sodium uranate system by thermodynamics calculation using Thermo-Calc.

Oral presentation

Development of fast reactor containment safety analysis code, CONTAIN-LMR; Validation study of sodium-concrete reaction model

Kawaguchi, Munemichi; Yamamoto, Ikuo; Seino, Hiroshi

no journal, , 

The CONTAIN-LMR code has been developed in Japan Atomic Energy Agency (JAEA) for the quantitative assessment of severe accident consequences in sodium-cooled fast reactor (SFR). We will present results of the development and validation for the sodium-concrete reaction model (SLAM) in this code.

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