Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 249

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Oral presentation

Fabrication and test results of testing equipment for remote-handling of MA fuel, 1; Testing equipment for fuel cooling

Sugawara, Takanori; Nishihara, Kenji; Tazawa, Yujiro; Tsujimoto, Kazufumi

no journal, , 

This presentation shows fabrication and test results of a testing facility for fuel cooling that is a component of the testing facility for remote-handling of highly-radioactive MA fuels in the transmutation physics experimental facility (TEF-P) planned in the J-PARC. Evaluation formula of pressure drop and temperature increase used in the design of TEF-P was validated by the test, and, feasibility of cooling concept was confirmed.

Oral presentation

Study on rapid analysis of the radioactive tritium in groundwater into the Fukushima-1 Nuclear Power Plant, 1; Applicability confirmation of the tritium column

Sasaki, Takayuki*; Akimoto, Yuji*; Seki, Kotaro; Nagano, Misato*; Ishimori, Kenichiro; Ueno, Takashi; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Uncertainty of criticality analysis of UO$$_{2}$$-concrete system under randomization

Ueki, Taro

no journal, , 

Analysis framework under indeterminate material distribution is investigated for the Monte Carlo (MC) criticality calculation of continuously mixed media formed via molten core concrete interaction. Randomized Weierstrass functions (RWF) are utilized to represent the volume fractions of constituent materials. The possibility of several percent fluctuation of effective multiplication factor is shown by the MC simulation with delta-tracking.

Oral presentation

Remote technology development for function advancement of research base, 7; Feasibility study of a portable Compton camera for visualizing radioactive substances

Sato, Yuki; Kishimoto, Aya*; Kaburagi, Masaaki; Kataoka, Jun*; Torii, Tatsuo

no journal, , 

no abstracts in English

Oral presentation

Effect of hydrocarbons on tritium oxidation reactor for ITER detritiation system

Edao, Yuki; Iwai, Yasunori; Sato, Katsumi; Hayashi, Takumi

no journal, , 

no abstracts in English

Oral presentation

Development of active neutron NDA techniques for nuclear non-proliferation, 3; Experimental evaluation of neutron flux distribution in the DDA system

Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi

no journal, , 

JAEA has started to develop a technology which can be applicable to high radioactive special nuclear materials such as next-generation fuel cycle products. We have been developed Non-destructive assay system Active-N as a test equipment which utilizes D-T neutron generator. In a system for Differential Die-Away (DDA) method which is tested in Active-N, it is important to evaluate neutron flux to check the performance of the system. In this research, we have evaluated neutron flux in a system for Fast Neutron Direct Interrogation method which is a kind of DDA method by activation method and Monte Carlo simulation by using PHITS.

Oral presentation

The Supports for local governments used the walking survey

Terunuma, Hirotaka; Tanaka, Kiwamu; Kabumoto, Hiroshi; Haginoya, Masashi; Sano, Naruto; Takahashi, Masatomi; Hoshino, Masato; Aoki, Isao; Asazuma, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Investigation of the chemical form of ruthenium compounds in the vitrification process, 4; RuO$$_{2}$$ generation by reaction with Ru-La-Na mix nitrates and raw materials for vitrification

Nagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro; Sato, Nobuaki*; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Seki, Katsumi*

no journal, , 

It is thought that a generated ruthenium compound grows from a high level radioactive liquid waste into RuO$$_{2}$$ crystal by reacting to raw materials for the vitrification process. In this study, the generation reaction to RuO$$_{2}$$ was confirmed by heating Ru-La-Na mix nitrates and the raw materials.

Oral presentation

Development of active neutron NDA techniques for nuclear non-proliferation, 4; Design study on NRTA technique for quantification of isotopes of nuclear materials

Tsuchiya, Harufumi; Kitatani, Fumito; Kureta, Masatoshi; Maeda, Makoto

no journal, , 

no abstracts in English

Oral presentation

Development of active neutron NDA techniques for nuclear non-proliferation, 2; Design study on DDA technique for nuclear materials

Ozu, Akira; Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Kureta, Masatoshi

no journal, , 

no abstracts in English

Oral presentation

Development of numerical simulation method for relocation behavior of molten materials in nuclear reactors, 6; Consideration of the melt diffusion model on interfaces

Yamashita, Susumu; Takase, Kazuyuki; Monji, Hideaki*; Yoshida, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Measurement of void fraction distribution in two-phase flow in a 4$$times$$4 bundle

Liu, W.; Nagatake, Taku; Jiao, L.; Shibata, Mitsuhiko; Komatsu, Masao*; Takase, Kazuyuki; Yoshida, Hiroyuki

no journal, , 

To improve and validate the prediction accuracy of two - phase codes, Japan Atomic Energy Agency is working on the measurement of void faction distribution in rod bundles with using wire mesh sensors, under high pressure and high temperature conditions (2MPa, 212$$^{circ}$$C). The test section is a 4$$times$$4 rod bundle, in which two three - layer 9$$times$$9 wire mesh sensors are installed at two different axial positions. As the first step of the experiment, to validate the measuring system, we performed experiments in water - air system under atmospheric pressure, with using water and air flow rates as parameters. Void fraction distributions in the sub-channels of the rod bundle were derived in a wide flow pattern from bubbly flow to slug flow. The water flow rate, from the viewpoint of considering the natural circulation after reactor scrum, was lower than 600 kg/m$$^{2}$$s. The data will be used to validate the void fraction correlations and two-phase evaluation codes.

Oral presentation

Two-phase flow measurement in an upward pipe flow using wire-mesh sensor technology

Jiao, L.; Takase, Kazuyuki; Liu, W.; Nagatake, Taku; Uesawa, Shinichiro; Yoshida, Hiroyuki; Shibata, Mitsuhiko

no journal, , 

To construct a database for upwards air/water flows in a vertical pipe, extensive measurements of air/water flows in a vertical pipe using the wire-mesh sensor technology were conducted at the thermal fluid dynamic test facility TPTF of the Japan Atomic Energy Agency. The test section is 4m in length and 58mm in inner diameter, two sets of three-layers-WMS were set separately at the 1.15m and 1.65m elevation of the air injection position. Air was injected from the bottom of the pipe through 0.6mm/1mm/2mm diameter nozzles. The obtained data are characterized particularly by their quantity and their detailed information on important two-phase flow parameters (e.g. radial distribution of the void fraction, the gas velocity and the time and cross-section averaged bubble size distribution for different test section heights). In the near future, we would like to use the WMS to measure the detailed two-phase flow in sub-channels of a simulated bundle flow.

Oral presentation

Oral presentation

First-principles study of hydride in zirconium

Itakura, Mitsuhiro; Okita, Taira*

no journal, , 

Time to hydride precipitation in Zircalloy fuel cladding determines the lifetime of the fuel cladding of nuclear reactors. For the design of a new reactor with increased irradiation to transmute TRU elements and reduce waste, the effect of irradiation on the hydride formation must be evaluated. We carried out ab-initio calculations of vacancy cluster and the segregation of hydrogen to the cluster to deduce the fundamental parameters for the modeling of hydride formation. The results are indispensable for the design of the new reactor.

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 2; Sensitivity analysis

Hirouchi, Jun; Takahara, Shogo; Watanabe, Masatoshi; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 1; Literature search on variation factors

Watanabe, Masatoshi; Takahara, Shogo; Hirouchi, Jun; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Development of non-destructive examination technique for fuel debris using X-ray computed tomography

Ishimi, Akihiro; Katsuyama, Kozo; Akasaka, Naoaki; Misawa, Susumu*

no journal, , 

no abstracts in English

249 (Records 1-20 displayed on this page)