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

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 nuclear data processing system FRENDY, 3; Construction of the probability table in the unresolved resonance region

Tada, Kenichi; Nagaya, Yasunobu

no journal, , 

JAEA has been developing the nuclear data processing code FRENDY (FRom Evaluated Nuclear Data librarY to any application). In this presentation, construction of the probability table in the unresolved resonance region is described.

Oral presentation

Analysis of PIE data of BWR fuel using SWAT4

Kikuchi, Takeo; Tada, Kenichi; Suyama, Kenya

no journal, , 

To estimate the prediction accuracy of the integrated burn up analysis code system SWAT4, we compared the calculation results of SWAT4 and the PIE data of the BWR fuel which was measured by JAERI in 1990s. Comparison results are indicated that the C/E value of major heavy nuclei, e.g., U and Pu, is approximately 1.0. The calculation results are also indicated that some fission products, e.g., Sm, have the larger difference.

Oral presentation

Applied example MCNP5 on ambient dose evaluation from nuclear facility

Zaima, Naoki; Naganuma, Masaki; Sakao, Ryota

no journal, , 

no abstracts in English

Oral presentation

Effect of halogenated gas on detritiation efficiency of the detritiation system

Iwai, Yasunori; Kondo, Akiko*; Edao, Yuki; Sato, Katsumi; Kubo, Hitoshi*; Oshima, Yusuke*

no journal, , 

Effect of halogenated gas on detritiation efficiency of the detritiation system has been investigated taking an event of off normal event such as fire into consideration. Concerning the activity of platinum catalyst for oxidation of tritium, we have evaluated the steep decrease in activity of platinum catalyst in the presence of halogenated gas. In order to avoid the steep decrease in activity, a noble catalyst alloyed with platinum and palladium showed an outstanding proof. In addition, the halogenated acid produced over catalyst surface affects the activity of catalyst. As for water absorber, a molecular sieve decreased its water absorbing capacity in the presence of halogenated gas.

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

Status of R&D of advanced neutron multiplier in ITER-BA activity, 20; Granulation and characteristics of Be-Zr beryllides pebbles

Kim, Jae-Hwan; Nakano, Suguru; Akatsu, Yoshiaki; Nakamichi, Masaru

no journal, , 

no abstracts in English

Oral presentation

Measurement of neutron-production double-differential cross sections in most-forward direction for 48-, 63- and 78-MeV proton incidences on lithium, carbon, aluminum, iron and lead targets

Satoh, Daiki; Iwamoto, Yosuke; Ogawa, Tatsuhiko

no journal, , 

Many neutrons are produced in forward directions by intermediate-energy proton-induced reactions. While it is known that collective motion in a target nucleus plays important role in this neutron production, validity of theoretical model and nuclear-data library has not been examined well due to a lack of experimental data. Hence, we obtained systematic data of neutron-production double-differential cross section in the most-forward direction. The experiment was performed at TIARA of Takasaki Advanced Radiation Research Institute, JAEA. 48-, 63-, and 78-MeV proton beams were bombarded upon thin lithium, carbon, aluminum, iron, and lead target, and the neutrons produced in the most-forward direction were led to experimental room passing through a collimator. Scintillation detectors were used to the neutron detection. The measured data for lighter nuclei such as Li, C, Al showed peak structures corresponding to energy levels of the nuclei. In the spectra for Pb, one can see a broad peak caused by the collective motion of the nucleus. In comparison with the calculation results of PHITS using a theoretical model INCL and a nuclear-data library JENDL-4.0/HE, it was found that the JENDL-4.0/HE reproduces the measure spectra better than the INCL does.

Oral presentation

R&D of MA separation processes for P&T system using ADS, 7; Examination of novel extractants for MA separation

Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi; Matsumura, Tatsuro

no journal, , 

JAEA continues to carry out the development of the ADS(Double-strata). Mutual separation of Am(III) and Cm(III) is important for the development of the partitioning process. The separation is particularly difficult, because they have the analogous chemical behavior. Alkyl diamide amine (ADAAM), a new high-performance reagent with a simple structure, was examined for the mutual separation of Am(III) and Cu(III). The combination of ADAAM and N,N,N',N'-tetraethyldiglycolamide (TEDGA) as a masking agent shows selectivity for Am(III) over Cm(III) in highly acidic media with separation factors up to 41.

Oral presentation

Measurement of the hydrogen concentration in the vessel off-gas generated radiolytically from Pu storage tanks

Hoshi, Takahiro; Nagaoka, Shinichi; Kudo, Atsunari; Ouchi, Masayuki; Isobe, Hiroyasu; Obu, Tomoyuki; Kurabayashi, Kazuaki

no journal, , 

no abstracts in English

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

249 (Records 1-20 displayed on this page)