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JAEA Reports

Development of $$^{93}$$Zr, $$^{93}$$Mo, $$^{107}$$Pd and $$^{126}$$Sn analytical methods for radioactive waste from Fukushima Daiichi Nuclear Power Station

Aono, Ryuji; Sato, Yoshiyuki; Shimada, Asako; Tanaka, Kiwamu; Ueno, Takashi; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Technology 2017-025, 32 Pages, 2017/11

JAEA-Technology-2017-025.pdf:1.45MB

We have developed analytical methods for $$^{93}$$Zr, $$^{93}$$Mo, $$^{107}$$Pd and $$^{126}$$Sn, which are considered important in terms of the safety assessment of radioactive waste disposal. The methods are specialized for the wastes left after Fukushima accident. As the main analytical sample, we assumed accumulated water / treated water collected at Fukushima Daiichi Nuclear Power Station. As for $$^{93}$$Zr, $$^{93}$$Mo, $$^{107}$$Pd and $$^{126}$$Sn contained in this accumulated water / treated water, we have worked on the development of separation and purification method of target nuclide and improvement of recovery, and summarized these results in this report.

Journal Articles

Radiochemical analysis of rubble collected from around and inside reactor buildings at Units 1 to 4 in Fukushima Daiichi Nuclear Power Station

Sato, Yoshiyuki; Aono, Ryuji; Konda, Miki; Tanaka, Kiwamu; Ueno, Takashi; Ishimori, Kenichiro; Kameo, Yutaka

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 13 Pages, 2017/00

no abstracts in English

Journal Articles

Radiochemical analysis of rubble collected from Fukushima Daiichi Nuclear Power Station

Sato, Yoshiyuki; Tanaka, Kiwamu; Ueno, Takashi; Ishimori, Kenichiro; Kameo, Yutaka

Hoken Butsuri, 51(4), p.209 - 217, 2016/12

A large amount of contaminated rubbles were generated by the accident at the Fukushima Daiichi Nuclear Power Station (F1NPS). For safe decommissioning of F1NPS, it is important to evaluate the composition and concentration of radionuclides in the rubbles. In this paper, to characterize the rubbles collected at F1NPS in Unit-1, Unit-2 and Unit-3, radiochemical analysis was operated. As a result of radiochemical analysis, $$gamma$$-ray-emitting nuclides $$^{60}$$Co, $$^{137}$$Cs and $$^{152,154}$$Eu, $$beta$$-ray-emitting nuclides $$^{3}$$H, $$^{14}$$C, $$^{90}$$Sr and $$^{99}$$Tc, and $$alpha$$-particle-emitting nuclides $$^{238,239+240}$$Pu, $$^{241}$$Am and $$^{244}$$Cm were detected. In contrast, $$^{94}$$Nb and $$^{152}$$Eu concentrations were below the detection limit. Measured radioactive concentrations implied that $$^{3}$$H, $$^{14}$$C, $$^{60}$$Co and $$^{90}$$Sr concentrations depended on $$^{137}$$Cs concentration respectively. This analysis was characterized the radioactivity concentrations of the rubbles.

JAEA Reports

Study on radionuclide analysis of rubble and plants for decommissioning of Fukushima Daiichi Nuclear Power Station

Seki, Kotaro; Sasaki, Takayuki*; Akimoto, Yuji*; Tokunaga, Takahito; Tanaka, Kiwamu; Haraga, Tomoko; Ueno, Takashi; Ishimori, Kenichiro; Hoshi, Akiko; Kameo, Yutaka

JAEA-Technology 2016-013, 37 Pages, 2016/07

JAEA-Technology-2016-013.pdf:2.09MB

In this study, based on the simple and rapid analytical method established from the wastes from research facilities, we created analytical schemes which is applicable to rubble and plants collected at Fukushima Daiichi, then transported to Nuclear Science Research Institute of JAEA. We examined the applicability, and confirmed quantifiability of radioactivity concentration with high recovery rate without being affected by fission products such as $$^{90}$$Sr and $$^{137}$$Cs.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities, 4

Omori, Hiroyuki; Nebashi, Koji; Shimada, Asako; Tanaka, Kiwamu; Yasuda, Mari; Hoshi, Akiko; Tsuji, Tomoyuki; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Data/Code 2014-029, 31 Pages, 2015/03

JAEA-Data-Code-2014-029.pdf:1.51MB

Simple and rapid methods to evaluate the radioactivity concentrations are required for the radioactive waste generated from research facilities in the Japan Atomic Energy Agency to dispose of in a near-surface repository. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid waste generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid waste generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In this report, we reported the analytical data determined in fiscal 2014 ($$^{137}$$Cs and $$^{93}$$Mo) and summarized them with the radioactivity concentrations obtained in the past as basic data to consider the evaluation method of radioactivity concentrations in the stored waste taken from JPDR.

Journal Articles

Radionuclide release to stagnant water in the Fukushima-1 Nuclear Power Plant

Nishihara, Kenji; Yamagishi, Isao; Yasuda, Kenichiro; Ishimori, Kenichiro; Tanaka, Kiwamu; Kuno, Takehiko; Inada, Satoshi; Goto, Yuichi

Journal of Nuclear Science and Technology, 52(3), p.301 - 307, 2015/03

 Times Cited Count:11 Percentile:17.53(Nuclear Science & Technology)

After the severe accident at the Fukushima-1 nuclear power plant, large amounts of contaminated stagnant water have accumulated in turbine buildings and their surroundings. This rapid communication reports calculation of the radionuclide inventory in the core, collection of measured inventory in the stagnant water, and estimation of radionuclide release ratios from the core to the stagnant water. This evaluation is based on data obtained before June 3, 2011. The release ratios of tritium, iodine, and cesium were several tens of percent, whereas those of strontium and barium were smaller by one or two orders of magnitude. The release ratios in the Fukushima accident were equivalent to those in the TMI-2 accident.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities, 3

Yasuda, Mari; Tanaka, Kiwamu; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Kameo, Yutaka

JAEA-Data/Code 2014-011, 59 Pages, 2014/08

JAEA-Data-Code-2014-011.pdf:16.84MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.

Journal Articles

Radiochemical analysis of rubble and trees collected from Fukushima Daiichi Nuclear Power Station

Tanaka, Kiwamu; Shimada, Asako; Hoshi, Akiko; Yasuda, Mari; Ozawa, Mayumi; Kameo, Yutaka

Journal of Nuclear Science and Technology, 51(7-8), p.1032 - 1043, 2014/07

 Times Cited Count:16 Percentile:12.97(Nuclear Science & Technology)

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities, 2

Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Higuchi, Hidekazu

JAEA-Data/Code 2013-008, 16 Pages, 2013/11

JAEA-Data-Code-2013-008.pdf:2.41MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.

Journal Articles

Radionuclide release to stagnant water in Fukushima-1 Nuclear Power Plant

Nishihara, Kenji; Yamagishi, Isao; Yasuda, Kenichiro; Ishimori, Kenichiro; Tanaka, Kiwamu; Kuno, Takehiko; Inada, Satoshi; Goto, Yuichi

Nippon Genshiryoku Gakkai Wabun Rombunshi, 11(1), p.13 - 19, 2012/03

After the severe accident in the Fukushima-1 Nuclear Power Plant, large amount of contaminated stagnant water has been produced in turbine buildings and those surroundings. This rapid communication reports calculation of radionuclide inventory in the core, collection of measured inventory in the stagnant water, and estimation of radionuclide release ratios from the core to the stagnant water. The present evaluation is based on data obtained before June 3, 2011.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities

Hoshi, Akiko; Tsuji, Tomoyuki; Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Sakai, Akihiro; Kameo, Yutaka; Kogure, Hiroto; Higuchi, Hidekazu; Takahashi, Kuniaki

JAEA-Data/Code 2011-011, 31 Pages, 2011/10

JAEA-Data-Code-2011-011.pdf:1.7MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data (262 data) about the radioactivity concentrations of the 7 important nuclides ($$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{59}$$Ni, $$^{63}$$Ni, $$^{90}$$Sr, $$^{137}$$Cs) which accumulated by the analysis.

Oral presentation

$$^{94}$$Nb analysis of metal waste samples generated from reactor facilities

Tanaka, Kiwamu; Yasuda, Mari; Haraga, Tomoko; Hoshi, Akiko; Kogure, Hiroto

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis in stagnant water in Fukushima-1 Nuclear Power Plant, 2; Analysis of Se-79, Sr-90, Tc-99

Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tanaka, Kiwamu; Kameo, Yutaka; Katayama, Atsushi; Higuchi, Hidekazu

no journal, , 

Analytical methods were developed for determination of Se-79, Sr-90 and Tc-99 in stagnant water generated from Fukushima-1 Nuclear Power Plant. The recoveries of these elements were enough to determine the concentrations of Se-79, Sr-90 and Tc-99. The interference of beta emitter could not be found by beta spectrometry. The present method could be applied to stagnant water.

Oral presentation

Study on the radiochemical method in stagnant water in Fukushima-1 Nuclear Power Plant

Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Katayama, Atsushi; Higuchi, Hidekazu; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis of waste debris and stagnant water in Fukushima-1 Nuclear Power Plan, 1; Analysis of $$gamma$$-ray emitting nuclides, H-3, C-14, Sr-90

Kameo, Yutaka; Tanaka, Kiwamu; Ozawa, Mayumi; Sato, Kenji; Unno, Toshimichi; Kimiyama, Kazuhiro; Seki, Shuhei; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis for treatment and disposal of rubble and trees generated by the Fukushima-1 nuclear power plant accident

Kameo, Yutaka; Tanaka, Kiwamu; Yasuda, Mari; Shimada, Asako; Ueno, Takashi; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis of living tree collected from Fukushima-1 Nuclear Power Station

Tanaka, Kiwamu; Ueno, Takashi; Yasuda, Mari; Shimada, Asako; Hoshi, Akiko; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Current situation of radionuclides analysis on Fukushima Daiichi Nuclear Power Station

Meguro, Yoshihiro; Kato, Jun; Kishimoto, Katsumi; Kameo, Yutaka; Ishimori, Kenichiro; Tanaka, Kiwamu; Shibata, Atsuhiro; Koma, Yoshikazu; Ashida, Takashi

no journal, , 

The authors are working in study for radioactive wastes generated in Fukushima Daiichi. Radioactive inventory estimation of wastes is important in the study for the processing and disposal of radioactive waste. And then so many real wastes have to be analyzed for their inventory evaluation. In addition to this waste analysis, there are several needs for analysis. For example a large volume of the contaminated water is being decontaminated, and operational status and ability of this system should be checked by analysis of the treated water. And also groundwater and sea water are analyzing to understand contaminated situation, to estimate a leakage position, and to confirm leakage prevention. In future fuel debris will be analyzed for its material accountancy. In this presentation, actual situation of analyses in Fukushima Daiichi will be explained, mainly focus on analyses for the inventory evaluation of the radioactive waste.

Oral presentation

The Supports for local governments used the walking survey

Terunuma, Hirotaka; Tanaka, Kiwamu; Kabumoto, Hiroshi; Haginoya, Masashi; Sano, Naruto; Takahashi, Masatomi; Hoshino, Masato; Aoki, Isao; Asazuma, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Study on analysis method of the palladium-107 in radioactive waste collected from the Fukushima Daiichi Nuclear Power Station

Sato, Yoshiyuki; Tokunaga, Takahito; Numayama, Satoru; Tanaka, Kiwamu; Ueno, Takashi; Ishimori, Kenichiro; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis of rubble collected from reactor buildings at Fukushima Daiichi Nuclear Power Station

Aono, Ryuji; Sato, Yoshiyuki; Konda, Miki; Tanaka, Kiwamu; Ueno, Takashi; Ishimori, Kenichiro; Kameo, Yutaka

no journal, , 

A large amount of contaminated rubble was generated by the accident at the Fukushima Daiichi Nuclear Power Station (F1NPS). For safe decommissioning of F1NPS, it is important to evaluate the composition and concentration of radionuclides in the rubble. To characterize the rubble collected at F1NPS, radiochemical analysis was conducted. From the rubble collected from reactor buildings, $$^3$$H, $$^{14}$$C, $$^{60}$$Co, $$^{63}$$Ni, $$^{79}$$Se, $$^{90}$$Sr, $$^{99}$$Tc, $$^{129}$$I, $$^{137}$$Cs, $$^{154}$$Eu, $$^{238, 239+240}$$Pu, $$^{241}$$Am and $$^{244}$$Cm were detected. The radioactivity concentrations of $$^{60}$$Co, $$^{90}$$Sr and $$^{238}$$Pu are correlated that of $$^{137}$$Cs. The radioactive ratio of $$^{60}$$Co/$$^{137}$$Cs, $$^{90}$$Sr/$$^{137}$$Cs and $$^{238}$$Pu/$$^{137}$$Cs were similar between the rubble collected from 1st floor and 5th floor of unit 1 reactor building. This result implied that regardless of sampling location in reactor building, the radioactive ratios of $$^{60}$$Co/$$^{137}$$Cs, $$^{90}$$Sr/$$^{137}$$Cs and $$^{238}$$Pu/$$^{137}$$Cs were consistent.

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