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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

Development of solidification techniques with minimised water content for secondary radioactive aqueous wastes in Fukushima, 1; Synthesis and evaluation of simulated wastes

Taniguchi, Takumi; Irisawa, Keita; Ito, Yuzuru; Namiki, Masahiro; Osugi, Takeshi; Abe, Tomohisa; Sato, Junya; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Estimation of source term for spent fuel disposal, 2; Effect of carbonate concentration on dissolution rate of UO$$_{2}$$ and spent fuel; A Review

Kitamura, Akira; Akahori, Kuniaki*

no journal, , 

Since dissolution rate of UO$$_{2}$$ matrices will be depend on carbonate concentration due to promoting oxidative dissolution of spent nuclear fuel by formation of carbonate complexes of uranium(VI), effect of carbonate concentration on dissolution rate of UO$$_{2}$$ and spent nuclear fuel has been reviewed. It is found that a systematic study on dissolution rate of UO$$_{2}$$ and/or spent fuel as a function of carbonate concentration is recommended.

Oral presentation

Characterization of fuel debris (28'A), 4; Characterization of simulated MCCI products by light-concentrating heating

Sudo, Ayako; Takano, Masahide; Onozawa, Atsushi

no journal, , 

To characterize the reaction layers with respective temperatures around core melt/concrete interface, we have performed MCCI experiments in laboratory scale by using a light-concentrating technique. As minor constituents, Gd$$_{2}$$O$$_{3}$$ (burnable poison and FP), Mo-Ru-Rh-Pd alloy (FP), and sea salt were added in the simulated MCCI debris. The analyses of the top part of the sample identified as-melted (U,Zr)O$$_{2}$$ particles precipitated in silicate glass containing U, Zr, Gd, Fe and Cr. Gd was included in both (U,Zr)O$$_{2}$$ and silicate glass and Mo and the platinum group elements formed alloys with Fe-Ni-Mo-Ru-Rh-Pd. Although almost sea salt evaporated and deposited on the belljar, some S originating from sea salt resulted in precipitation of FeS-type sulfide in the alloy.

Oral presentation

Numerical analysis of effects by environmental factors on HT- and HTO-transfer

Yamazawa, Hiromi*; Moriizumi, Jun*; Atarashi-Andoh, Mariko

no journal, , 

no abstracts in English

Oral presentation

Temporal changes in the vertical distribution of ($$^{137}$$Cs) in forest soils after the Fukushima Dai-ichi Nuclear Power Plant accident; Observations and model analysis

Muto, Kotomi; Atarashi-Andoh, Mariko; Koarashi, Jun; Matsunaga, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Application of dose coefficients for internal exposures based on Caucasian physique to Japanese

Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki

no journal, , 

Effective doses based on ICRP 2007 Recommendations are evaluated from sex averaged equivalent doses obtained by using reference male and female phantoms (male: RCP-AM, female: RCP-AF) whose physique and organ masses (physical characteristics) are adjusted to the reference values of Caucasians. ICRP is revising dose coefficients for internal exposure (committed effective doses per unit intake of radionuclides) conforming to the Recommendations. It is important to comprehend the extent of underestimate or overestimate of doses for Japanese males and females, whose physical characteristics are different from those of Caucasians, when the dose coefficients revised by the ICRP are adopted to the Japanese system of radiation protection. In this study, we evaluated the dose coefficients for ingestion and inhalation of radionuclides based on the average adult Japanese male and female phantoms (male: JM-103, female: JF-103), which have the average physical characteristics of Japanese males and females, and compared the Japanese dose coefficients with sex-averaged dose coefficients based on RCP-AM and RCP-AF. As a result, the differences in dose coefficients were within plus or minus 10% in cases of 87% and 73% for JM-103 and JF-103, respectively. Therefore, the cases that lead considerable underestimation or overestimation from the point of view of radiation protection are limited even if the sex-averaged dose coefficients based on Caucasian physical characteristics are applied to Japanese males and females.

Oral presentation

A Simulation study of personal dose equivalent for external exposure to radioactive cesium distributed in soil

Satoh, Daiki; Furuta, Takuya; Takahashi, Fumiaki; Bolch, W. E.*; Lee, C.*

no journal, , 

In the guidance to return to the areas where the evacuation orders have been lifted, the Nuclear Regulation Authority made a statement that the radiation dose of returnees should be assessed based on individual monitoring instead of spatial monitoring with the ambient dose equivalent. The individual monitoring of external exposure is usually performed with a personal dosimeter worn on a body, and the dosimeter indicate a personal dose equivalent Hp(10). Hence, the relationship of the personal dose equivalent to the ambient dose equivalent and the effective dose in the environment contaminated with the radioactive cesium must be quantified to control the radiation exposure of the residents. In the present work, the age-dependent personal dose equivalent is analyzed for the radioactive cesium distributing in soil at a depth of 0.0, 0.5, 2.5, 10.0, and 50.0 g/cm$${^2}$$ by means of the radiation transport code PHITS and the computational phantoms representing the newborn; 1-year old, 5-year old, 10-year old, and 15 year old children, and adults. From the results, it was found that the personal dose equivalent provides an acceptable assessment for the effective dose, and does not exceed the ambient dose equivalent in the contaminated environment.

Oral presentation

Comprehensive benchmark calculations of the latest version of the PHITS code

Iwamoto, Yosuke; Sato, Tatsuhiko; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuda, Norihiro; Hosoyamada, Ryuji*; Niita, Koji*

no journal, , 

Particles and Heavy Ions Transport code System (PHITS) is used for various purposes such as accelerator shielding design, medical physics calculations, and so on. In this study, we performed benchmark calculations for particle production cross sections (47 cases), neutron transport (6 cases) and electro-magnetic cascade (12 cases). For calculations of particle production cross sections, PHITS reproduced the experimental data for high-energy particle incident reactions with energies of above 100 MeV. On the other hands, PHITS did not reproduce the data for low-energy incident reactions due to outside of scope for the intra nuclear cascade model INCL4. We will incorporate the evaluated nuclear data library JENDL4.0/HE with PHITS to solve the problem. For calculations of electro-magnetic cascade, PHITS reproduced the data well. As a result, we validated the accuracy of PHITS calculations for various applied area and obtained guidelines for effective improvement of PHITS.

Oral presentation

Investigations of mineral alteration in Kunigel V1 samples contacted with iron obtained from long-term in-situ experiments

Ishidera, Takamitsu; Sasamoto, Hiroshi; Sato, Hisao*

no journal, , 

no abstracts in English

Oral presentation

Structure of hydrated Cs on montmorillonite

Okamoto, Takuya*; Okubo, Takahiro*; Iwadate, Yasuhiko*; Deguchi, Kenzo*; Shimizu, Tadashi*; Oki, Shinobu*; Tachi, Yukio

no journal, , 

The structures of Cs adsorbed on montmorillonite were investigated by $$^{133}$$Cs Magic Angle Spinning (MAS) NMR spectroscopy. The NMR spectra of Cs adsorbed on montmorillonite samples were measured under different relative humidity levels and were analyzed to evaluate the change in the structure of hydrated Cs sorbed on montmorillonite.

Oral presentation

Pore distribution of water-saturated compacted clay using NMR relaxometry

Yamazaki, Akio*; Okubo, Takahiro*; Iwadate, Yasuhiko*; Tachi, Yukio

no journal, , 

A structural analysis of water-filled pores in saturated compacted sodium montmorillonite was conducted by 1H NMR spectroscopy. The pore structure including interlayer and intraparticle pores in compacted montmorillonite was characterized by relaxation time and freezing point observed by 1H NMR and their correlations with water-filled pore sizes.

Oral presentation

Derivation of approximate analytical solutions for the nuclides release from engineered barrier system of radioactive waste disposal and understanding of response characteristics of the system, 1; Derivation of approximate analytical solution for the nuclides release from EBS with the double diffusion media and the response characteristics

Oi, Takao; Takahashi, Hirokazu*

no journal, , 

Availability of analytical solution for the disposal study of the radioactive waste and the method for utilization to the disposal study of the wastes arising from Fukushima Daiichi NPS will introduced. Also, derivation of approximate analytical solution for the nuclides release from EBS with the double diffusion media and the response characteristics will be presented.

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.

265 (Records 1-20 displayed on this page)