JOPSS - Search Results

Oral presentation

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 1; Synthesis characteristics of lithium zirconates from (U,Zr)O $_{2}$ with molten LiCl-Li $_{2}$ O

Nakayoshi, Akira; Kitawaki, Shinichi; Sakamura, Yoshiharu*; Uruga, Kazuyoshi*; Tanaka, Takeshi*

no journal, ,

no abstracts in English

Oral presentation

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 1; Investigation of influence of lithium zirconates

Nakayoshi, Akira; Kitawaki, Shinichi; Kofuji, Hirohide; Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Uruga, Kazuyoshi*; Ando, Hidekazu*

no journal, ,

no abstracts in English

Oral presentation

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 2; Electrolytic reduction tests for simulated fuel debris

Sakamura, Yoshiharu*; Uruga, Kazuyoshi*; Ando, Hidekazu*; Kitawaki, Shinichi; Nakayoshi, Akira; Kofuji, Hirohide

no journal, ,

no abstracts in English

Oral presentation

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 3; Chlorination experiments of simulated fuel debris by use of zirconium chloride

Uruga, Kazuyoshi*; Murakami, Tsuyoshi*; Sakamura, Yoshiharu*; Nakayoshi, Akira; Kitawaki, Shinichi; Kofuji, Hirohide

no journal, ,

no abstracts in English

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 9; Internal heating type drying test of zeolite packed in transparent vessel model

Uruga, Kazuyoshi*; Tsukada, Takeshi*; Yamagishi, Isao; Terada, Atsuhiko; Uchiyama, Hideaki*

no journal, ,

CIPPEI fabricated a small scale model of the spent zeolite adsorption vessel in Fukushima Nuclear Power Plant and performed to heating test at the center of the zeolite filling bed. As a result, the chloride concentration at the bottom of vessel decreases as time has passed. Chlorine concentrated around the adsorption vessel center.

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 8; External heating type drying test of zeolite packed in small SUS vessel

Yamagishi, Isao; Kato, Chiaki; Nagaishi, Ryuji; Arisaka, Makoto; Uruga, Kazuyoshi*; Tsukada, Takeshi*

no journal, ,

no abstracts in English

Oral presentation

Absorption and lifting of salt water by zeolite

Uruga, Kazuyoshi*; Tsukada, Takeshi*; Terada, Atsuhiko; Yamagishi, Isao

no journal, ,

For the safe storage of zeolite wastes generated by the treatment of radioactive saline water at the Fukushima Daiichi Nuclear Power Station, this study investigated the fundamental transport properties of water and chloride in zeolite column.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 14; Cesium volatilization from inorganic absorbents during heat treatment

Uruga, Kazuyoshi*; Furukawa, Shizue*; Koyama, Tadafumi*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, ,

no abstracts in English

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 16; Numerical simulation of inner used zeolite vessel including permeation model of remained contaminated water

Uruga, Kazuyoshi*; Tsukada, Takeshi*; Yamagishi, Isao; Terada, Atsuhiko

no journal, ,

The inside of the zeolite adsorption tower used for the treatment of contaminated water at the Fukushima Daiichi Nuclear Power Station is predicted during storage. As a result of constructing a model based on the test results and performing numerical analysis on the evaporation/condensation of the residual water inside and the permeation into the zeolite, it showed that the salt contained in the residual water was concentrated in the center of the adsorption vessel. Then, the salinity in the residual water decreased.

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 15; Salt deposition on zeolite after the full-scale drying test

Sagawa, Yusuke*; Yamagishi, Isao; Terada, Atsuhiko; Uruga, Kazuyoshi*; Tsukada, Takeshi*

no journal, ,

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 25; Evaluation of glass composition range suitable for solidification of secondary wastes from treatment of the contaminated water

Koyama, Tadafumi*; Uruga, Kazuyoshi*; Furukawa, Shizue*; Vienna, J.*; Parruzot, B.*; Xiaonan, L.*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, ,

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 26; Investigation of approach for selecting solidification techniques applied to contaminated water management waste, 3

Furukawa, Shizue*; Koyama, Tadafumi*; Uruga, Kazuyoshi*; Kikuchi, Michio*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, ,

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 27; Cesium volatilization from used inorganic absorbents

Uruga, Kazuyoshi*; Furukawa, Shizue*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, ,

no abstracts in English

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Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 1; Synthesis characteristics of lithium zirconates from (U,Zr)O $_{2}$ with molten LiCl-Li $_{2}$ O

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 1; Investigation of influence of lithium zirconates

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 2; Electrolytic reduction tests for simulated fuel debris

Applicability of pyro-reprocessing technologies to the treatment of fuel debris, 3; Chlorination experiments of simulated fuel debris by use of zirconium chloride

Consideration for long-term storage of a spent zeolite adsorption vessel, 9; Internal heating type drying test of zeolite packed in transparent vessel model

Consideration for long-term storage of a spent zeolite adsorption vessel, 8; External heating type drying test of zeolite packed in small SUS vessel

Absorption and lifting of salt water by zeolite

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 14; Cesium volatilization from inorganic absorbents during heat treatment

Consideration for long-term storage of a spent zeolite adsorption vessel, 16; Numerical simulation of inner used zeolite vessel including permeation model of remained contaminated water

Consideration for long-term storage of a spent zeolite adsorption vessel, 15; Salt deposition on zeolite after the full-scale drying test

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 25; Evaluation of glass composition range suitable for solidification of secondary wastes from treatment of the contaminated water

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 26; Investigation of approach for selecting solidification techniques applied to contaminated water management waste, 3

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 27; Cesium volatilization from used inorganic absorbents