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Oral presentation

Optical transport property of alternative He-3 neutron detector using solid ceramic scintillators

Ozu, Akira; Takase, Misao*; Haruyama, Mitsuo; Kurata, Noritaka*; Kobayashi, Nozomi*; Tobita, Hiroshi; Kureta, Masatoshi; Nakamura, Tatsuya; To, Kentaro; Suzuki, Hiroyuki; et al.

no journal, , 

no abstracts in English

Oral presentation

Evaluation of neutron nuclear data on tellurium isotopes

Shibata, Keiichi

no journal, , 

Although JENDL-4.0 was released in 2010, the high-energy cross sections of about 40 FP nuclides were not re-examined due to the time limit. Tellurium is one of such data which were not revised in the high-energy region. Considering the significance of the activation cross sections of tellurium, the present work was undertaken to evaluate the neutron cross sections of $$^{120-132}$$Te in the energy from 10$$^{-5}$$ eV to 20 MeV. The statistical model code CCONE, which was based on the Hauser-Feshbach theory, was used to evaluate cross sections above 10 eV. Parameters required as input to the CCONE code were determined by reflecting the latest knowledge on nuclear physics. As for the neutron optical model parameters, we employed the values obtained by Kunieda et al. using the coupled-channel method. The evaluated results reproduce existing experimental data very well.

Oral presentation

Investigation of glass structure and cesium redox state in simulated waste glass by Raman spectroscopy and synchrotron XAFS measurement

Nagai, Takayuki; Okamoto, Yoshihiro; Kano, Shigeru; Nishizawa, Daiji; Seki, Katsumi*; Homma, Masanobu*; Kobayashi, Hiromi*; Ayame, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Elemental analysis of simulated waste glass by laser ablation ICP-AES, 4; Verification of quantitative analysis of various elements in simulated waste glass

Inose, Takehiko*; Nishizawa, Daiji; Oyama, Koichi; Miyauchi, Atsushi; Nagai, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Detailed analysis of two-phase flow behavior on pool scrubbing

Okagaki, Yuria; Shibamoto, Yasuteru; Sun, Haomin; Satou, Akira; Yonomoto, Taisuke

no journal, , 

no abstracts in English

Oral presentation

Meteorological observation around nuclear facility by Doppler Lidar

Nakano, Masanao

no journal, , 

Since the remote sensing technique for the meteorological observation has been developing these years, the Doppler Lidar is available in the commercial market. Although some investigation organizations carried out the examination on the method and application of Doppler Lidars and had generally good results, the duration of the examination was limited in a short period. So it is unknown whether the Doppler Lidar is applicable to the long-term meteorological observation in the nuclear facilities to assess the public dose around nuclear facilities. Therefore, the long-term performance and applicability of a small Doppler Lidar has been examined. As the result, the Doppler Lidar was satisfied with the national guideline, and the data at 100 m above sea level had a good relationship with the propeller data,. Additionally, the Doppler Lidar could obtain the data even in the storm condition. From this fact, the Doppler Lidar used in this examination is considered to have a practicability for the dose assessment of the public.

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 2; Effects of a control material of boron for FP transport behavior

Sato, Isamu; Onishi, Takashi; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Ishigamori, Toshio*; Seki, Takayuki*; Shinada, Masanori*; et al.

no journal, , 

As a material simulating FP, CsI was heated and evaporated to be decomposited on the surface of a tube having a temperature gradient. Gaseous B$$_{2}$$O$$_{3}$$ made by heating it at higher temperature was react with CsI decomposited on the surface, and then the boron effects for decomposition and migration behavior of Cs and I were observed. Consequently, it was indicated that boron vapor could strip decomposited CsI to make it gaseous species again and then the guseous CsI could move to the colder position.

Oral presentation

Study on failure evaluation of reactor pressure vessel lower head due to severe accidents, 6-1; Failure evaluation by thermal-hydraulics and structural analyses

Katsuyama, Jinya; Yamaguchi, Yoshihito; Kaji, Yoshiyuki; Yoshida, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 9; Forest fire hazard assessment methodology

Okano, Yasushi; Yamano, Hidemasa

no journal, , 

There has been an increased concern in the safety of NPP for external hazards, one of which is a forest fire. Conventional forest fire assessments have been performed with deterministic and conservative manner, using so-called envelope initial and boundary conditions on forest fire analyses. In this study, the forest fire hazard assessment methodology, which is subject to an external-hazard probabilistic risk assessment (PRA), is being developed in order to quantitatively evaluate frequency and consequence of the forest fire that has a potential impact on a NPP and then to obtain the Core Damage Frequency. The new methodology based on a logic tree is developed in this study, as well as the sensibility analyses on weather conditions.

Oral presentation

Development of remote decontamination techniques for reactor building, 8; Analysis of Concrete core sample from Operation Floor of Unit 2

Higashiuchi, Atsushi; Maeda, Koji; Otani, Akira; Sasaki, Shinji; Katsuyama, Kozo; Chigira, Takayuki*; Murata, Hirotoshi*

no journal, , 

no abstracts in English

Oral presentation

Air dose rate distributions around the Fukushima Dai-ichi NPP Site and exposure doses

Saito, Kimiaki

no journal, , 

no abstracts in English

Oral presentation

The In-situ experiment for verification of performance of engineered barrier system in Horonobe Underground Research Laboratory, 9; Application of low alkaline cement for concrete plug

Nakayama, Masashi; Miura, Norihiko*; Ishida, Tomoko*; Takeda, Nobufumi*; Niunoya, Sumio*; Jo, Mayumi*

no journal, , 

no abstracts in English

Oral presentation

Corrosion property of reduced activation ferritic steel in flowing high temperature and high pressure water

Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Enoeda, Mikio

no journal, , 

no abstracts in English

Oral presentation

Determination of $$^{237}$$Np in spent nuclear fuel using anion-exchange porous polymeric filter

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

no journal, , 

no abstracts in English

Oral presentation

Increase in activity of hydrophobic platinum catalyst for oxidation of tritium by irradiation with electron beams

Iwai, Yasunori

no journal, , 

Hydrophobic platinum catalysts have been widely applied in the field of nuclear fusion such as to the exchange reactions of hydrogen isotopes between hydrogen and vapor and to the oxidation reactions of tritium. Hydrophobic platinum catalysts are hardly susceptible to water mist and water vapor. Hydrophobic platinum catalysts are produced by supporting platinum directly on hydrophobic polymer beads. For the hydrophobic polymer, styrene divinyl benzene (SDB) has been applied in Japan. It can be pointed out that the betterment in catalytic activity of hydrophobic catalyst is expected to downsize the catalytic reactor based on a hard look at a large increase in flow rate in future. The acute change in catalytic activity of two types of commercial Pt/SDB catalysts was found when they were irradiated with electron beams. After irradiation with electron beams, the catalytic activity was evaluated by means of overall reaction rate constant for the oxidation of tritium. The overall reaction rate constant increased as increase in dose. The constant showed the peak value in the dose between 500 to 1000 kGy. After the peak, the constant decreased as increase in dose. The overall reaction rate constant at the peak was 6 times larger than that evaluated with unirradiated. The mechanical strength of irradiated Pt/SDB kept sound until 1500 kGy. The irradiation is a promising method to the betterment in catalytic activity of Pt/SDB catalyst.

Oral presentation

Study on thermal influence of MA-containing MOX fuel characteristics on fuel performance

Kamei, Miho; Ozawa, Takayuki

no journal, , 

The future fast reactor (FR) cycle system to reduce radioactive waste volume by recycling Pu and minor actinides (MA), and it is important to evaluate the influence of high Pu content and MA content on oxide fuel performance. In this study, we investigated the influence of fuel characteristics on power-to-melt (PTM) from a viewpoint to prevent fuel melting. As a result, PTM of FR oxide fuel with high Pu content and MA content would be affected by fuel properties due to fuel composition, but it revealed that a correlation between fuel specifications and PTM in MA-containing MOX fuel would be similar to that in MOX fuel, and it can be mentioned that thermal performance of MA-containing MOX fuel would be secured to be equal to that of conventional MOX fuels by providing suitable fuel specifications up to MA content of 5 wt.%.

262 (Records 1-20 displayed on this page)