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Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 15; Progress in JFY2015 and event sequence assessment methodology against a combination hazard of strong wind and rainfall

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

no journal, , 

PRA and margin assessment methodologies have been developed for sodium-cooled fast reactors against representative external hazards. This report describes the overview of last year (JPY2015) updates and the development of the sequence assessment methodology against a combination hazard of strong wind and rainfall.

Oral presentation

Extension of nuclear evaluation code AMUR based on the resonance theory

Kunieda, Satoshi

no journal, , 

Evaluated cross-sections are fundamental quantities for nuclear science and engineering. In the resonance region, experimental activity is being increased using the J-PARC facility to measure the neutron cross-sections on the isotopes including LLFP and MA in this country. However, for the analysis/evaluation of measured data, we are still relying on the foreign codes which have advantages and disadvantages on the theoretical calculation and correction for the experimental conditions. The purpose of this work is to develop a new analysis code based on the R-matrix theory with high applicability and extensibility to the experimental conditions, by modifying an existing code AMUR. In this talk, we present current status of the code development on the calculation of the capture cross-sections and options for correction to measured data, together with some example analysis for the neutron cross-sections.

Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 17; Combination hazard curve evaluation of forest fire and thunder

Okano, Yasushi; Yamano, Hidemasa

no journal, , 

For an evaluation of a combination hazard curve of forest fire and thunder, it is necessary to take into account not only the overlap occurrence frequency but also meteorological effect on a forest fire intensity. The logic tree of a forest fire hazard curve evaluation was utilized in this study for quantitative estimation of the hazard curve of the combination event of forest fire and thunder.

Oral presentation

Experimental evaluation of primary yields of water radiolysis in seawater and its concentrated systems

Nagaishi, Ryuji; Kondo, Takafumi*; Godo, Masao*; Yoshida, Yoichi*; Inoue, Masao

no journal, , 

no abstracts in English

Oral presentation

Study on optimum thickness of moderator used in differential die-away analysis in active neutron NDA system

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

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Response measurement of neutron dose equivalent monitors from 96- to 387-MeV quasi-monoenergetic neutron fields

Nakane, Yoshihiro; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Nunomiya, Tomoya*; Sato, Tatsuhiko; Matsumoto, Tetsuro*; Masuda, Akihiko*; Yashima, Hiroshi*; Nakamura, Takashi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors, 2; Experimental study on molten-metal discharge into a shallow water pool

Imaizumi, Yuya; Kamiyama, Kenji; Matsuba, Kenichi; Isozaki, Mikio; Suzuki, Toru; Emura, Yuki

no journal, , 

For the study of the fuel-coolant interaction and deposition behavior of the molten core material on the in-vessel structure in the relocation phase of the core disruptive accident in SFR, several experiments discharging low-melting-point alloy into a shallow water pool were conducted. The experimental results and the mechanism discussion are reported.

Oral presentation

Research on neutron capture cross-sections of Cs isotopes in ImPACT project, 1; R&D plan

Nakamura, Shoji; Kimura, Atsushi; Hales, B. P.; Iwamoto, Osamu; Tsubata, Yasuhiro; Matsumura, Tatsuro

no journal, , 

As a part of research items on ImPACT Project, nuclear data research group of JAEA has performed the research on neutron capture cross-section measurements of Cs isotopes, especially Cs-135. This presentation gives an outline of research plans and their progress.

Oral presentation

Calculation of nuclear level density using the microscopic statistical model with Hartree-Fock-Bogoliubov theory

Furutachi, Naoya; Minato, Futoshi; Iwamoto, Osamu

no journal, , 

The nuclear level density is essential for nuclear reaction calculations using the statistical model and pre-equilibrium models. Phenomenological Fermi gas models have been used widely for calculations of the nuclear level density, however, reliability of them depend on the parameter adjustment to reproduce the experimental informations of the s-wave neutron resonance spacing D0, and therefore, calculations using more microscopic models are desirable for unstable nuclei that have no available experimental information. The microscopic statistical models and combinatorial models based on Hartree-Fock theory are models that can reproduce the experimental D0 with precisions comparable to the phenomenological models. However, these calculations are strongly dependent on the strength of the pairing interaction, and its uncertainty affect to the precision of the calculations. Therefore, in this work, we improved the treatment of the pairing interaction in the nuclear structure calculation, and analyzed how the pairing interaction affect to the precision of the nuclear level density calculation.

Oral presentation

Generation of an MVP library with a nuclear data processing system FRENDY

Nagaya, Yasunobu; Tada, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Spectroscopic measurements of X rays and $$gamma$$ rays emitted from $$^{237}$$Np sources with using TES microcalorimeters

Yasumune, Takashi; Takasaki, Koji; Ito, Chikara; Ono, Masashi*; Irimatsukawa, Tomoya*; Takahashi, Hiroyuki*

no journal, , 

no abstracts in English

Oral presentation

Effect of atmosphere on sintering behavior of (U,Ce)O$$_{2}$$

Nakamichi, Shinya; Hiroka, Shun; Kato, Masato; Sunaoshi, Takeo*; Nelson, A.*; McClellan, K.*

no journal, , 

Sintering behavior of (U$$_{0.70}$$Ce$$_{0.30}$$)O$$_{2}$$ was estimated and compared with that of MOX. Sintering of (U$$_{0.70}$$Ce$$_{0.30}$$)O$$_{2}$$ in CO$$_{2}$$ was not accelerated in contrast with that of MOX.

Oral presentation

Characterization of fuel debris (28'A), 9; Oxidation behavior of simulated fuel debris

Nishina, Masahiro; Hiroka, Shun; Morimoto, Kyoichi

no journal, , 

no abstracts in English

Oral presentation

Research on neutron capture cross-sections of Cs isotopes in ImPACT project, 2; Measurement of the neutron capture cross-section of $$^{133}$$Cs

Hales, B. P.; Nakamura, Shoji; Kimura, Atsushi; Iwamoto, Osamu

no journal, , 

no abstracts in English

Oral presentation

Mapping project in Fukushima and related researches, 1; Summary on temporal change of air dose rates and radionuclide deposition densities in the 80 km zone

Saito, Kimiaki; Mikami, Satoshi; Ando, Masaki; Matsuda, Norihiro; Tsuda, Shuichi; Yoshida, Tadayoshi; Yoshimura, Kazuya; Sato, Tetsuro*; Kanno, Takashi; Yamamoto, Hideaki

no journal, , 

no abstracts in English

Oral presentation

Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor, 1; Outline of model V&V and UQ procedure

Ohgama, Kazuya; Ikeda, Kazumi*; Ishikawa, Makoto; Kan, Taro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor, 2; Verification

Ikeda, Kazumi*; Kan, Taro*; Maruyama, Shuhei; Ohgama, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Mapping project in Fukushima and related researches, 7; Dose estimation of artificial / natural radioisotopes by an analysis of photon energy spectrum

Tsuda, Shuichi; Tanigaki, Minoru*; Saito, Kimiaki

no journal, , 

A GPS-aided radiation monitoring system KURAMA and the KURAMA-II developed by Kyoto University has been utilized after the Fukushima Dai-ichi Nuclear Power Plant accident in a mapping project of radionuclides deposited in the environment and monitoring of dose rates in air. KURAMA-II has a function of precisely evaluating dose rates in air based on measured pulse-height spectra from the incorporated CsI(Tl) scintillation detector. In this study, to evaluate dose contribution of the radionuclides in the environment, photon energy spectra was estimated by an unfolding method, using the measured pulse-height spectra and the dataset of the calculated response functions of the CsI(Tl) scintillation detector in a simulative environment. The results of dose contributions of artificial and natural radionuclides based on the estimation method will be reported in the session, "Mapping project in Fukushima and related researches".

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in the JRTF, 8; Cutting of lower part of the LV-1 tank

Yokozuka, Yuta; Mimura, Ryuji; Fujikura, Toshiki; Nemoto, Koichi; Shida, Shigeo

no journal, , 

no abstracts in English

265 (Records 1-20 displayed on this page)