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Journal Articles

General overview of the research project investigating the radionuclide solution behavior in mock mortar matrix modeled after conditions at the Fukushima-Daiichi Nuclear Power Station

Igarashi, Go*; Haga, Kazuko*; Yamada, Kazuo*; Aihara, Haruka; Shibata, Atsuhiro; Koma, Yoshikazu; Maruyama, Ippei*

Journal of Advanced Concrete Technology, 19(9), p.950 - 976, 2021/09

https://doi.org/10.3151/jact.19.950
 Times Cited Count：5 Percentile：39.74(Construction & Building Technology)

Journal Articles

A Project focusing on the contamination mechanism of concrete after the accident at Fukushima Daiichi Nuclear Power Plant

Yamada, Kazuo*; Maruyama, Ippei*; Haga, Kazuko*; Igarashi, Go*; Aihara, Haruka; Tomita, Sayuri*; Kiran, R.*; Osawa, Norihisa*; Shibata, Atsuhiro; Shibuya, Kazutoshi*; et al.

Proceedings of International Waste Management Symposia 2021 (WM2021) (CD-ROM), 10 Pages, 2021/03

Journal Articles

New project on the analysis of contamination mechanisms of concrete at the Fukushima Daiichi Nuclear Power Station

Yamada, Kazuo*; Maruyama, Ippei*; Koma, Yoshikazu; Haga, Kazuko*; Igarashi, Go*; Shibuya, Kazutoshi*; Aihara, Haruka

Proceedings of International Waste Management Symposia 2019 (WM2019) (CD-ROM), 6 Pages, 2019/03

Journal Articles

Decontamination of radioactive concrete waste and reuse of aggregate using pulsed power technology

Sakamoto, Hiroyuki*; Akagi, Yosuke*; Yamada, Kazuo*; Tachi, Yukio; Fukuda, Daisuke*; Ishimatsu, Koichi*; Matsuda, Mikiya*; Saito, Nozomi*; Uemura, Jitsuya*; Namihira, Takao*; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 17(2), p.57 - 66, 2018/05

https://doi.org/10.3327/taesj.J16.037

Concrete debris contaminated with radioactive cesium and other nuclides have been generated from the accident in the Fukushima Dai-ichi Nuclear Power Plant and there will be generated due to the decommissioning of nuclear power plants in the future. Although conventional decontamination techniques are effective for flat concrete surfaces such as floors and walls, it is not clear what techniques to apply for decontaminating radioactive concrete debris. In this study, focusing on a pulsed power discharge technique, fundamental experimental works were carried out. Decontamination of concrete by applying the aggregate recycling technique using the pulsed power discharge technique was evaluated by measuring radioactivity of aggregate and sludge separated from the contaminated concrete. The results suggest that the separation into aggregate and sludge of the contaminated concrete debris could achieve decontamination and volume reduction of the radioactive concrete debris.

JAEA Reports

Data on plutonium sorption onto rock; Results of the experiment for data on plutonium sorption onto tuff under conditions of reducing and of presence of nitrate

Suguro, Toshiyasu; Nishikawa, Yoshiaki*; Komuro, Takashi*; Kagawa, Akio; Kashiwazaki, Hiroshi; Yamada, Kazuo

JAEA-Technology 2007-058, 20 Pages, 2007/11

JAEA-Technology-2007-058.pdf:3.26MB

For safety assessment of TRU waste disposal, data on sorption data of plutonium on Tuff have been obtained by a static batch-type experiment. Because the repository condition will be reducing and be affected by considerable amount of nitrate in waste, the authors carried out the experiments using Tuff under the reducing (Na$$_{2}$$S$$_{2}$$O$$_{4}$$ as added as reductant) and anoxic condition (O$$_{2}$$$$leq$$1 ppm) and solution of 0 to 0.5 M NaNO$$_{3}$$. The experimental results suggest that distribution coefficient (Kd) ranges 0.2 to 0.7 m$$^{3}$$ kg$$^{-1}$$ in case of L/S=0.1 m$$^{3}$$ kg$$^{-1}$$. Similarly the Kd ranges, 1 to 7 m$$^{3}$$ kg$$^{-1}$$ at L/S=1 m$$^{3}$$ kg$$^{-1}$$. However, almost samples of the solution after experiments were plutonium solubility less than detection limit(10$$^{-13}$$mol/dm$$^{3}$$) of alpha spectrometer. The reason, it is guessed plutonium coprecipitation with calcium hydroxide, because experiments using saturated calcium hydroxide in the liquid.

JAEA Reports

Study on dissolution behavior of plutonium from Pu-doped glass

Kuroha, Mitsuhiko; ; Yamada, Kazuo; Yui, Mikazu; *; *

JNC TN8410 98-001, 35 Pages, 1998/10

JNC-TN8410-98-001.pdf:2.79MB

In order to study the migration behavior of plutonium from high-level vitrified waste in a deep repository condition, plutonium doped simulated high-level vitrified waste was prepared in a laboratory. Pu-doped glass was prepared with 1wt.% of PuO$$_{2}$$. The simulated high-level vitrified waste was crushed to less than 75$$mu$$m and put into platinum crucible ($$phi$$17 mm $$times$$ 80 mm) with PuO$$_{2}$$ powder sieved to less than 75$$mu$$m. The crucible was set into an electric furnace and the temperature was raised up to 1300 $$^{circ}$$C and kept for 2 hours. The melt was cooled down after annealing at 650 $$^{circ}$$C for 2 hours. The specimen was cut and homogeneity of Pu in Pu-doped glass was observed by $$alpha$$-autoradiography. As a result of observation, plutonium was distributed homogeneously in the middle of the glass, but was distributed heterogeneously in the bottom of glass. And then the whole of the glass was crushed and melted again in the same way. Leaching experiments of Pu-doped glass and solubility experiments of Pu were carried out under aerobic conditions at room temperature. Leaching experiments of Pu-doped glass were carried out by using batch method with NaNO$$_{3}$$ solution. The particle size of glass powder was under 75$$mu$$m and pH were adjusted by HNO$$_{3}$$ and NaOH in the pH range 4-10. The experimental period was 151-340 days. Solubility experiments of Pu were also carried out from over saturation in 0.1M NaNO$$_{3}$$ solution and pH were adjusted by HNO$$_{3}$$ and NaOH in the pH range 4-12. The experimental period was 42-233 days. These leachate were filtered through a 10,000 molecular weight cut off (MWCO) ultrafilter to separate solution and solid. These experiments were carried out in the teflon vessel. The Pu concentration in leachate was analyzed by $$alpha$$-spectrometry. The Pu concentration from the Pu-doped glass was around 10$$^{-6}$$ mol/l in the pH range 4-6, and decreased to 10$$^{-9}$$ mol/l with increasing pH. The leaching ...

JAEA Reports

Measurement of glass transition temperature of waste glass by differential thermal analysis (DTA); Research report on solidification of high-level liquid waste

Ouchi, Jin; ; Kawamura, Kazuhiro; *; ; Sasage, Kenichi; Odakura, Makoto

PNC TN8410 97-044, 53 Pages, 1997/03

PNC-TN8410-97-044.pdf:1.36MB

The glass transition temperature of simulated waste glass was measured by DTA installed in CPF (Chemical Processing Facility) and HTS (High Level Waste Technology Section). This measurement was intended to confirm the agreement between hot and cold data as a part of characterization of high level waste glass. Glass transition temperature is an index of the temperature to keep thermal stability of high-level waste glass. Since devitrification deteriorates characteristics of waste glass above glass transition temperature, it is necessary to measure glass transition temperature and keep glass temperature below glass transition temperature. The conventional method to determine glass transition temperature is the measurement of thermal expansion, but DTA is adopted for radioactive sample because of easier preparation. We obtained following results by measuring glass transition temperature of simulated waste glasses after calibration with standard specimen : (1)The average glass transition temperature of TVF waste glass (P0798) measured by DTA in HTS and CPF was 494$$^{circ}$$C (standard deviation 3 $$sigma$$: 8.2$$^{circ}$$C) and 495$$^{circ}$$C (3$$sigma$$: 1.8$$^{circ}$$C), respectively. The difference between two analyzer was 1$$^{circ}$$C. It shows the good agreement between hot and cold DTA data. (2)Glass transition temperature of P0798 measured by thermal expansion method was 495$$^{circ}$$C(3$$sigma$$: 8.1$$^{circ}$$C) and it agrees well with that measured by DTA. (3)The average glass transition temperature of simulated highly waste-loading glass (P1102) measured by DTA in HTS and CPF was 510.5 $$pm$$2.5$$^{circ}$$C.

JAEA Reports

None

Odakura, Makoto; *; Yamada, Kazuo; Ishikawa, Hirohisa; Kikuchi, Hiroshi*; ; Ishiguro, Katsuhiko

PNC TN8410 97-015, 30 Pages, 1997/01

PNC-TN8410-97-015.pdf:2.02MB

None

JAEA Reports

None

Myochin, Munetaka; Kosugi, Kazumasa; Wada, Yukio; Yamada, Kazuo; Seimiya, Hiroshi; Ishikawa, Hirohisa

PNC TN8410 96-071, 86 Pages, 1996/03

PNC-TN8410-96-071.pdf:35.04MB

None

JAEA Reports

Development of thermocouple re-instrumentation technique for irradiated fuel rod; Techniques for making center hole into UO$$_{2}$$ pellets and thermocouple re-instrumentation to fuel rod

; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.

JAERI-Tech 95-037, 87 Pages, 1995/07

JAERI-Tech-95-037.pdf:5.14MB

no abstracts in English

Journal Articles

Effects of alpha decay on the properties of actual nuclear waste glass

Bamba, Tsunetaka; ; Muraoka, Susumu; Yamada, Kazuo*; Saito, Makoto*; Ishikawa, Hirohisa*; Sasaki, Noriaki*

Materials Research Society Symposium Proceedings, Vol.353, p.1397 - 1404, 1995/00

no abstracts in English

JAEA Reports

None

Saito, Makoto; Yamada, Kazuo; Kitano, Mitsuaki; Kuroha, Mitsuhiko; Seimiya, Hiroshi

PNC TN8410 92-056, 43 Pages, 1992/03

PNC-TN8410-92-056.pdf:3.74MB

None

JAEA Reports

None

Ashida, Takashi; Sonobe, Hitoshi; Yamada, Kazuo

PNC TN8600 91-003, 38 Pages, 1991/06

PNC-TN8600-91-003.pdf:4.17MB

no abstracts in English

JAEA Reports

None

Seimiya, Hiroshi; Yamada, Kazuo; Kuroha, Mitsuhiko; Saito, Makoto; Tomikawa, Hirofumi; Saito, Toru*; Hagiya, Shinichi*

PNC TN8410 90-082, 90 Pages, 1990/09

PNC-TN8410-90-082.pdf:6.81MB

None

Journal Articles

Development of the Engineered Barriers for the Deep Geological Disposal of High-Level Radioactive Waste

Sasaki, Noriaki; Ishikawa, Hirohisa; Miyahara, Kaname; Yamada, Kazuo; Yusa, Yasuhisa

High Level Radioactive Waste Management 1990, p.675 - 682, 1990/00

JAEA Reports

None

Sasaki, Noriaki; Yusa, Yasuhisa; *; *; 14 of others*

PNC TN8440 89-022, 29 Pages, 1989/11

PNC-TN8440-89-022.pdf:4.2MB

None

Journal Articles

Study of the Performance of Solidified High-Level Waste Forms and Engineered Barriers under Reposit

; Sasaki, Noriaki; Yusa, Yasuhisa; Yamada, Kazuo; Miyahara, Kaname; Arai, Takashi

IAEA Research Co-ordination Meeting on the "Perfo, 0 Pages, 1989/00

JAEA Reports

None

Sasaki, Noriaki; Yusa, Yasuhisa; Yamada, Kazuo; Nodaka, Masayuki*; *; Kawamura, Kazuhiro; Miyahara, Kaname; Arai, Takashi; Kamei, Gento; Hirose, Ikuro; et al.

PNC TN8440 88-018, 170 Pages, 1988/12

PNC-TN8440-88-018.pdf:11.35MB

None

JAEA Reports

None

Sasaki, Noriaki; Yusa, Yasuhisa; *; *; Tsukane, Kenichi*; *; Idemitsu, Kazuya*; *

PNC TN8510 88-005, 294 Pages, 1988/08

PNC-TN8510-88-005.pdf:8.04MB

no abstracts in English

JAEA Reports

None

*; Arai, Takashi*; Tsukane, Kenichi

PNC TN4510 88-006, 461 Pages, 1988/05

PNC-TN4510-88-006.pdf:46.01MB

None

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