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Journal Articles

Diffusion and retention behaviour of Cs in illite-added compacted montmorillonite

Ishidera, Takamitsu; Kurosawa, Seiichi*; Hayashi, Masanori*; Uchikoshi, Keiji*; Beppu, Hikari*

Clay Minerals, 51(2), p.161 - 172, 2016/05

 Times Cited Count:4 Percentile:13.89(Chemistry, Physical)

The sorption and diffusion behavior of Cs in illite-added compacted montmorillonite was investigated by through-diffusion experiment. The obtained distribution coefficient of Cs for the illite-added compacted montmorillonite was several times larger than that for the montmorillonite without illite, while no increase of effective diffusion coefficient was observed for the illite-added compacted montmorillonite. The dominant sorption site of Cs on illite is considered to be the frayed edge site (FES) considering the Cs concentration in this experiment. Therefore, the surface diffusion of Cs sorbing on the FES on illite surface was considered to be negligible in compacted montmorillonite.

Journal Articles

Development of calculation code for estimating radiation dose for hypothetical accident of nuclear facility considering radioactive decay chain during atmospheric dispersion of released radionuclides

Takeyasu, Masanori; Nakano, Masanao; Sumiya, Shuichi; Nemoto, Hiromi*; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

Proceedings of 3rd Asian and Oceanic Congress on Radiation Protection (AOCRP-3) (CD-ROM), 4 Pages, 2010/05

The dose to the public at hypothetical accident of nuclear facility is estimated on the basis of the method described in the Japanese meteorological guideline. However, the radioactive decay during atmospheric dispersion of released radionuclide is not considered in the calculation formula in the guideline. Therefore, when the radionuclide of the half life such as a few min is released, the dose may be excessively over-estimated. In this study, the calculation code was developed which could consider the radioactive decay of the released radionuclide and the generation of the product. The dose calculated on the basis of the developed code was compared with that on the basis of the guideline.

JAEA Reports

Oral presentation

Development of determination for a trace of $$gamma$$ nuclides in the high radioactive Cs component samples by the Solid-phase extraction disk for removal of Cs /$$gamma$$ spectrometry

Yamazaki, Yuki*; Okano, Masanori; Jitsukata, Shu*; Kuno, Takehiko; Kurosawa, Akira

no journal, , 

no abstracts in English

Oral presentation

Effect of dry density on activation energy of effective diffusion coefficient for deuterated water in compacted bentonite

Ishidera, Takamitsu; Kurosawa, Seiichi*; Otsuka, Shunji*; Hayashi, Masanori*; Uchikoshi, Keiji*; Suzuki, Yasuyuki*

no journal, , 

no abstracts in English

Oral presentation

Determination of technetium-99 in liquid wastes of Fukushima-Daiichi Nuclear Power Plant by solid extraction-ICP AES method

Suwa, Toshio; Okano, Masanori; Jitsukata, Shu*; Nemoto, Hirokazu*; Kuno, Takehiko; Kurosawa, Akira

no journal, , 

no abstracts in English

Oral presentation

Evaluation of distribution coefficients for radionuclides sorption on bentonite colloid

Ishidera, Takamitsu; Kurosawa, Seiichi*; Hayashi, Masanori*; Suzuki, Yasuyuki*

no journal, , 

In the geological disposal of high-level radioactive waste (HLW) in Japan, potential impact of bentonite colloid on the migration of radionuclides needs to be evaluated in the performance assessment of geological disposal. Japan Atomic Energy Agency (JAEA) has been investigating sorption behavior of radionuclides on bentonite colloid and developing the evaluation model for the radionuclide sorption behavior on bentonite colloid. In our previous studies, the sorption behavior of Cs and Am on bentonite colloid was well interpreted by the evaluation model based on a previously reported sorption model for non-colloidal bentonite. In the presentation, the evaluation model for distribution coefficient of radionuclides sorption on bentonite colloid will be introduced in detail and the application result of evaluation model to the sorption behavior of Np on bentonite colloid will be shown.

Oral presentation

Investigation of sorption reversibility of Np(V) on bentonite colloid

Nakata, Kotaro*; Ishidera, Takamitsu; Kurosawa, Seiichi*; Hayashi, Masanori*; Beppu, Hikari*; Sukegawa, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Investigation of sorption reversibility of Am(III) and the other nuclides on bentonite colloids

Nakata, Kotaro*; Ishidera, Takamitsu; Kurosawa, Seiichi*; Hayashi, Masanori*; Beppu, Hikari*; Sukegawa, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Study on the generation process of radioactive particles emitted from Unit 1 of FDNPP

Ishii, Tatsuya*; Sueki, Keisuke*; Matsuo, Kazuki*; Kurosawa, Masanori*; Satou, Yukihiko; Kobata, Masaaki; Fukuda, Tatsuo; Yoshii, Kenji; Tanida, Hajime; Okane, Tetsuo; et al.

no journal, , 

Radioactive particles were released into the environment by the accident of Fukushima Daiichi Nuclear Power Plant (FDNPP). They have information to understand the inside of the reactor during the accident. Now, nobody knows the generation process of radioactive particles. In this study, we analyzed (1) elements of particles' cross section with SEM-EDS to reveal what is the material and (2) chemical states of elements on particles' surface with HAXPES. (1) Radioactive particles are composed of the two parts. One is the basic material and the other is the heavy elemental materials. We considered the basic material was soda-lime glass and the heavy elemental materials included lead glass. (2) HAXPES brought out that the chemical states of Cs on particles, surface was different in the Na-poor areas and the Na-rich areas. In the Na-poor areas, the chemical state of Cs showed CsFeSiO$$_4$$ mainly, but zero valence partly. In the Na-rich areas, the chemical state of Cs couldn't be identified. For above analyses, we can reveal the generation process of radioactive particles.

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