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Oral presentation

Evaluation of $$gamma$$-ray induced nuclear data

Iwamoto, Nobuyuki

no journal, , 

Photonuclear data are required in the field for, e.g., shielding design of high-energy electron linear accelerator, high-energy $$gamma$$-ray therapy, and non-destructive assay. This work aims at developing photonuclear reaction data file with a wide range of nuclides for more extensive use. In order to perform evaluation in the $$gamma$$-ray energy up to 140 MeV, nuclear reaction model calculation code CCONE was used. The modified Lorentzian model was applied to describe giant dipole resonance. The resonance parameters were fixed by reproducing photoabsorption data. The quasi-deuteron model was also taken into account in this present code. The nuclear level density was adopted from Gilbert-Cameron formalism with Mengoni-Nakajima Fermi-gas model. The evaluated results were compared with the measured data, JENDL/PD-2004 and KAERI data and showed good agreements with the measured data. These evaluated data are planned to be included into the next photonuclear data file.

Oral presentation

High-energy nuclear data library JENDL-4.0/HE

Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.

no journal, , 

Neutron- and proton-induced evaluated nuclear data are required in a wide energy range for the design of accelerator applications. New evaluations are performed with recent progresses in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p + $$^{6,7}$$Li and p + $$^{8}$$Be which are highly requested from medical field. Our present high-energy nuclear data library, JENDL-4.0/HE, includes cross-sections for 132 nuclei up to 200 MeV. In this talk, we present the evaluation methods, evaluated double-differential cross-sections and results of benchmark calculations.

Oral presentation

Measurement of neutron capture cross section of Gd-155 and 157 with the NaI(Tl) spectrometer in J-PARC/MLF/ANNRI

Kimura, Atsushi; Nakamura, Shoji; Terada, Kazushi; Nakao, Taro; Toh, Yosuke; Harada, Hideo; Igashira, Masayuki*; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Takamiya, Koichi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 10; Progress in JFY2014 and event sequence assessment methodology against volcanic eruption hazards

Yamano, Hidemasa; Nishino, Hiroyuki; Kurisaka, Kenichi; Okano, Yasushi; Sakai, Takaaki; Yamamoto, Takahiro*; Ishizuka, Yoshihiro*; Furukawa, Ryuta*; Geshi, Nobuo*; Nanayama, Futoshi*; et al.

no journal, , 

PRA and margin assessment methodologies are being developed for sodium-cooled fast reactors against representative external hazards. This report describes the overview of Third-year (JPY2014) updates and the development of the sequence assessment methodology against volcanic eruption hazard.

Oral presentation

Estimation of impact of difference in nuclear reaction models in PHITS on nuclear characteristics of accelerator-driven system

Iwamoto, Hiroki; Nishihara, Kenji; Iwamoto, Yosuke; Hashimoto, Shintaro; Sato, Tatsuhiko

no journal, , 

no abstracts in English

Oral presentation

High-temperature strength anisotropy map of SiC/SiC composites

Nozawa, Takashi; Park, J.-S.*; Nakazato, Naofumi*; Ozawa, Kazumi; Tanigawa, Hiroyasu

no journal, , 

Silicon carbide is a candidate nuclear materials because of low-activation and superior irradiation resistance as well as perceived various characteristics inherently featured as prominent engineering ceramics and a continuous fiber reinforced composite has generally been developed due to brittleness of SiC itself. Of many material parameters for design, validation of high temperature durability at approximately 1000$$^{circ}$$C is essential. Understanding of anisotropy of woven composite strength is also very important. Besides, developing comprehensive model to predict composite strength by various modes with a limited data set. This study aims to summarize the features of fracture behavior by tensile, compressive and shear at elevated temperatures. With consideration of the prediction model, we finally obtain the high temperature strength anisotropy map.

Oral presentation

Introduction of JAWAS-N as active neutron measurement device and its practical use for actual uranium waste, 1; Validation items for material accountancy

Nakatsuka, Yoshiaki; Zaima, Naoki; Nakashima, Shinichi; Fujiki, Naoki*; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao

no journal, , 

The historical procedures and target of active neutron measurements devices will be reported beside requirements of SG/MA tools. Also introduced the principles of FNDI methods and its applicability.

Oral presentation

Introduction of JAWAS-N as active neutron measurement device and its practical use for actual uranium waste, 2; performances of operation, maintenance and radiation safety

Fujiki, Naoki*; Nakatsuka, Yoshiaki; Zaima, Naoki; Nakashima, Shinichi; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao

no journal, , 

The performances of methodological characteristics, operation stability and radiation control of active neutron measurements devices will be reported.

Oral presentation

Study on the minor actinide transmutation utilizing Monju data, 8-2; Systematic compilation and evaluation of measurement data with the MA transmutation

Yokoyama, Kenji; Ishikawa, Makoto; Numata, Kazuyuki; Usami, Shin; Takeda, Toshikazu*

no journal, , 

no abstracts in English

Oral presentation

Introduction of JAWAS-N as active neutron measurement device and its practical use for actual uranium waste, 3; Validation tests for detection characteristics

Suwaki, Takuro*; Zaima, Naoki; Nakatsuka, Yoshiaki; Fujiki, Naoki*; Nakashima, Shinichi; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao

no journal, , 

The mockup tests used standard uranium source and simulated matrices have been successfully performed. The well performances of this device are introduced.

Oral presentation

Introduction of JAWAS-N as active neutron measurement device and its practical use for actual uranium waste, 4; Measurement trial for actual uranium bearing waste drums

Zaima, Naoki; Nakatsuka, Yoshiaki; Nakashima, Shinichi; Fujiki, Naoki*; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao

no journal, , 

The trials for measuring actual waste drums have been performed, and validated good applicability active neutron measurements device on site.

Oral presentation

Development of quantitative analysis apparatus of tritium in a high accuracy

Edao, Yuki; Iwai, Yasunori; Hayashi, Takumi

no journal, , 

no abstracts in English

Oral presentation

Technology and development for nuclear forensics; Result of ITWG collaborative materials exercise

Okubo, Ayako; Shinohara, Nobuo; Toda, Nobufumi; Kataoka, Osamu; Matsumoto, Tetsuya

no journal, , 

no abstracts in English

Oral presentation

Characterization of fuel debris (27'A), 2; Mechanical properties of Fe$$_{2}$$(Zr,U)

Hoshino, Takanori; Ikeuchi, Hirotomo; Suzuki, Seiya; Okamura, Nobuo; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Oral presentation

R&D of MA separation processes for P&T system using ADS, 5; Examination of Novel Extractants for MA/Ln 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 MA and Ln is important for the development of the partitioning process. The separation is particularly difficult, because they have the analogous chemical behavior. New reagent was synthesized and examined. The results of separation factors (SF) of Am against Eu are more than 25, SFAm/Cm = 5.5. The reagent is very stable chemically, high extraction capacity, fully miscible with hydrocarbon diluents, fast chemical kinetics, and following the CHON-principle.

Oral presentation

Investigation of the chemical form of ruthenium compounds in the vitrification process, 3; Reactions of lanthanide nitrates and ruthenium nitrates included in a liquid waste

Nagai, Takayuki; Sasage, Kenichi; Oyama, Koichi; Sato, Nobuaki*; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*

no journal, , 

no abstracts in English

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant, 20; Prediction of ambient dose equivalent rates

Kinase, Sakae; Takahashi, Tomoyuki*; Sato, Satoshi*; Yamamoto, Hideaki; Saito, Kimiaki

no journal, , 

no abstracts in English

Oral presentation

Approach for biosphere modeling according to surface environmental conditions

Nagao, Fumiya; Kato, Tomoko; Suzuki, Yuji*; Itazu, Toru*

no journal, , 

The basic matrices were compiled structurally which contain transport and exposure processes in the surface environment. And the method was shown to construct the steady-state biosphere model by combination of the basic matrices. To confirm applicability of the method, a dry run of the biosphere modeling for the hypothetical site was conducted.

Oral presentation

Study on removal technologies for Fukushima's fuel debris using laser light, 14; Characteristic evaluation for laser cutting process of thick metal plates by an adaptive control system

Hanari, Toshihide; Yamada, Tomonori; Matsunaga, Yukihiro; Nguyen, P. L.; Nakamura, Masaki; Muramatsu, Toshiharu

no journal, , 

no abstracts in English

266 (Records 1-20 displayed on this page)