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JAEA Reports

Analysis of the radioactivity concentrations in radioactive waste generated from JRR-2 and JRR-3 and Stored at the Waste Storage Facility L as compressed packages

Kinase, Akari; Goto, Katsunori*; Aono, Ryuji; Konda, Miki; Sato, Yoshiyuki; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Data/Code 2024-004, 60 Pages, 2024/07

JAEA-Data-Code-2024-004.pdf:2.05MB

Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field as trench and pit. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until the beginning of disposal. In order to contribute to this work, we collected and analyzed the samples generated from JRR-2 and JRR-3 and stored at the waste storage facility L. In this report, we summarized the radioactivity concentrations of 20 radionuclides ($$^{3}$$H, $$^{14}$$C, $$^{36}$$Cl, $$^{60}$$Co, $$^{63}$$Ni, $$^{90}$$Sr, $$^{94}$$Nb, $$^{99}$$Tc, $$^{108m}$$Ag, $$^{129}$$I, $$^{137}$$Cs, $$^{152}$$Eu, $$^{154}$$Eu, $$^{234}$$U, $$^{238}$$U, $$^{238}$$Pu, $$^{239}$$Pu, $$^{240}$$Pu, $$^{241}$$Am, $$^{244}$$Cm) which were obtained from radiochemical analysis of the samples in fiscal year 2022.

Journal Articles

Determination of $$^{90}$$Sr in highly radioactive aqueous samples via conversion to a kinetically stable 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid complex followed by concentration-separation-fractionation based on capillary electrophoresis-liquid scintillation

Ouchi, Kazuki; Haraga, Tomoko; Hirose, Kazuki*; Kurosawa, Yuika*; Sato, Yoshiyuki; Shibukawa, Masami*; Saito, Shingo*

Analytica Chimica Acta, 1298, p.342399_1 - 342399_7, 2024/04

 Times Cited Count:0 Percentile:0.01

Given that conventional methods of high-dose sample analysis pose substantial exposure risks and generate large amounts of secondary radioactive waste, faster procedures allowing for decreased radiation emission are highly desirable. To address this need, we developed a $$^{90}$$Sr$$^{2+}$$ quantitation technique that is based on liquid scintillation counting-coupled capillary transient isotachophoresis (ctITP) with two-point detection and relies on the rapid concentration, separation, and fractionation of 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA)-complexed $$^{90}$$Sr$$^{2+}$$ in a single run. This method, which allows for the handling of high-dose radioactive specimens at the microliter level and is substantially faster than conventional ion-exchange protocols, was used to selectively quantify $$^{90}$$Sr$$^{2+}$$ in real high-dose waste. The successful concentration-separation in ctITP was ascribed to the inertness of the Sr-DOTA complex to dissociation.

Journal Articles

Americium(III)/curium(III) complete separation and sensitive fluorescence detection by capillary and gel electrophoresis using emissive hexadentate/octadentate polyaminocarboxylate ligands

Saito, Shingo*; Haraga, Tomoko; Marumo, Kazuki*; Sato, Yoshiyuki; Nakano, Yuta*; Tasaki-Handa, Yuiko*; Shibukawa, Masami*

Bulletin of the Chemical Society of Japan, 96(3), p.223 - 225, 2023/03

Highly efficient and effective separation between americium (Am$$^{3+}$$) and curium ion (Cm$$^{3+}$$) was achieved by two simple electrophoresis-based techniques. Am$$^{3+}$$ and Cm$$^{3+}$$ ions were complexed with fluorophore-modified acyclic hexadentate and octadentate polyaminocarboxylates and then were electrophoretically separated and fluorescently detected in free solution with ternary complexation or in gel medium.

JAEA Reports

Waste liquid treatment for uranium liquid waste containing impurities

Sato, Yoshiyuki; Aono, Ryuji; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Testing 2019-003, 20 Pages, 2019/12

JAEA-Testing-2019-003.pdf:2.08MB

In the Radioactive Waste Management Technology Section, the radioactive liquid waste generated in the test using natural uranium in the past has been stored based on the contents of permission. Although we decided to perform solidification treatment in order to reduce the risk in storage, no rational treatment method has been established so far. Therefore, we examined adsorption treatment of natural uranium using uranium adsorbent (Tannix), and finally stabilized treatment by cement solidification. The treatment methods and findings obtained for a series of operations in waste liquid treatment are summarized in this report for reference when treating similar liquid waste.

Journal Articles

Safe and rapid development of capillary electrophoresis for ultratrace uranyl ions in radioactive samples by way of fluorescent probe selection for actinide ions from a chemical library

Haraga, Tomoko; Ouchi, Kazuki; Sato, Yoshiyuki; Hoshino, Hitoshi*; Tanana, Rei*; Fujihara, Takashi*; Kurokawa, Hideki*; Shibukawa, Masami*; Ishimori, Kenichiro; Kameo, Yutaka; et al.

Analytica Chimica Acta, 1032, p.188 - 196, 2018/11

 Times Cited Count:13 Percentile:48.12(Chemistry, Analytical)

The development of safe, rapid and highly sensitive analytical methods for radioactive samples, especially actinide (An) ions, represents an important challenge. Here we propose a methodology for selecting appropriate emissive probes for An ions with very low consumption and emission of radioactivity by capillary electrophoresis-laser-induced fluorescence detection (CE-LIF), using a small chemical library of probes with eight different chelating moieties. It was found that the emissive probe, which possesses the tetradentate chelating moiety, was suitable for detecting uranyl ions. The detection limit for the uranyl-probe complex using CE-LIF combined with dynamic ternary complexation and on-capillary concentration techniques was determined to be 0.7 ppt. This method was successfully applied to real radioactive liquid samples collected from nuclear facilities.

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

Development of simple and rapid analytical method for radioactive samples by capillary electrophoresis

Haraga, Tomoko; Sato, Yoshiyuki; Kameo, Yutaka; Saito, Shingo*

Dekomisshoningu Giho, (55), p.22 - 27, 2017/03

no abstracts in English

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.

Journal Articles

Application of capillary electrophoresis with laser-induced fluorescence detection for the determination of trace neodymium in spent nuclear fuel using complexation with an emissive macrocyclic polyaminocarboxylate probe

Haraga, Tomoko; Saito, Shingo*; Sato, Yoshiyuki; Asai, Shiho; Hanzawa, Yukiko; Hoshino, Hitoshi*; Shibukawa, Masami*; Ishimori, Kenichiro; Takahashi, Kuniaki

Analytical Sciences, 30(7), p.773 - 776, 2014/07

 Times Cited Count:7 Percentile:24.86(Chemistry, Analytical)

A simple and rapid method with low radiation exposure risk was developed for the determination of neodymium in spent nuclear fuel by CE with LIF detection using a fluorescent ligand having a macrocyclic hexadentate polyaminocarboxylate structure. The concentration of Nd(III) in a spent nuclear fuel sample was determined with no interference from various matrix elements, including lanthanides and uranium (at a 200-fold excess), with 92 $$pm$$ 3% recovery. This is due to method's high resolution based on establishing a ternary complex equilibrium during migration in which the hydroxyl ion plays an auxiliary role.

Journal Articles

Three-dimensional and multienergy $$gamma$$-ray simultaneous imaging by using a Si/CdTe Compton camera

Suzuki, Yoshiyuki*; Yamaguchi, Mitsutaka; Odaka, Hirokazu*; Shimada, Hirofumi*; Yoshida, Yukari*; Torikai, Kota*; Sato, Takahiro; Arakawa, Kazuo*; Kawachi, Naoki; Watanabe, Shigeki; et al.

Radiology, 267(3), p.941 - 947, 2013/06

 Times Cited Count:23 Percentile:64.71(Radiology, Nuclear Medicine & Medical Imaging)

Journal Articles

Highly sensitive detection of neodymium ion in small amount of spent nuclear fuel samples using novel fluorescent macrocyclic hexadentate polyaminocarboxylate probe in capillary electrophoresis-laser-induced fluorescence detection

Saito, Shingo*; Sato, Yoshiyuki*; Haraga, Tomoko; Nakano, Yuta*; Asai, Shiho; Kameo, Yutaka; Takahashi, Kuniaki; Shibukawa, Masami*

Journal of Chromatography A, 1232, p.152 - 157, 2012/04

 Times Cited Count:15 Percentile:47.11(Biochemical Research Methods)

A rapid and high-sensitive detection method of total concentration of Nd ion in a spent nuclear fuel sample is desirable since precise quantification of total Nd is useful as indicator of burnup. In this work, a capillary electrophoresis-laser-induced fluorescent detection method (CE-LIF) was proposed for analysis of total Nd in the spent fuel sample solution, employing a newly synthesized metal fluorescent probe with a fluorescein and a macrocylic hexadentate chelating group, FTC-ABNOTA, for lanthanide (Ln) ions. The mutual separation among the Ln-FTC-ABNOTA complexes was achieved by pH control providing dynamic ternary complexation with hydroxide ions. In this method, high resolution of Nd from other Ln ions with high resolution of 1.3-1.9 and a very low detection limit of 3.2 ppt were successfully obtained. A simulated spent fuel sample containing various metal ions was examined, so that a good quantification result with 99.3% recovery was obtained even with large excess of U.

Journal Articles

Three-dimensional imaging test for a head module of a Si/CdTe Compton camera for medical application

Yamaguchi, Mitsutaka; Kawachi, Naoki; Kamiya, Tomihiro; Sato, Takahiro; Suzui, Nobuo; Fujimaki, Shu; Odaka, Hirokazu*; Ishikawa, Shinnosuke*; Kokubun, Motohide*; Watanabe, Shin*; et al.

JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 145, 2012/01

no abstracts in English

Journal Articles

Basic characteristics of a newly developed Si/CdTe Compton camera for medical imaging

Kawachi, Naoki; Watanabe, Shigeki; Sato, Takahiro; Arakawa, Kazuo; Takeda, Shinichiro*; Ishikawa, Shinnosuke*; Aono, Hiroyuki*; Watanabe, Shin*; Yamaguchi, Mitsutaka*; Takahashi, Tadayuki*; et al.

2008 IEEE Nuclear Science Symposium Conference Record (CD-ROM), p.1540 - 1543, 2008/10

Patent

蛍光性ウラン錯体を形成する化合物、その合成方法、ウラン測定用蛍光プロープ及びウランの測定方法

原賀 智子

齋藤 伸吾*; 佐藤 義行*

JP, 2012-034711  Patent licensing information  Patent publication (In Japanese)

【課題】ウランを含む廃液及び廃棄物中のウランの安価な装置による定性分析法及び定量分析法で使用されるウラン測定用蛍光プローブとなる化合物を提供する。 【解決手段】下記式で示される化合物。(化学式のため省略)

Patent

Compound for forming fluorescent uranium complex, method for synthesizing thereof, fluorescent probe for detecting uranium and method for analyzing uranium

原賀 智子

齋藤 伸吾*; 佐藤 義行*

JP, 13/748953  Patent licensing information  Patent publication (In Japanese)

Disclosed is a compound suitable for use as a fluorescent probe for the detection of uranium. The compound enables the qualitative and quantitative analysis of uranium present in waste samples using less expensive apparatuses. The compound of the present invention has the structure shown by the following formula.

Patent

アメリシウム及びキュリウムの分離及び定量分析方法

原賀 智子; 佐藤 義行

齋藤 伸吾*

JP, 2014-063074  Patent licensing information  Patent publication (In Japanese)

【課題】安定な蛍光性アメリシウム錯体及び蛍光性キュリウム錯体を形成するアメリシウム及びキュリウム測定用蛍光プローブを提供する。 【解決手段】アメリシウム及びキュリウム測定用蛍光プローブが下記式(1)(化学式のため省略)で示される化合物がアルカリ性水溶液に溶解されて得られる。

Oral presentation

Study on analytical method of Sn-126 in accident waste collected from the Fukushima Daiichi Nuclear Power Station

Aono, Ryuji; Sato, Yoshiyuki; Ishimori, Kenichiro; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Americium-241 analysis for plutonium age dating purposes at the Environmental Sampling Laboratory, IAEA

Bujak, R.*; Sato, Yoshiyuki; Katona, R.*; Konegger-Kappel, S.*; Koepf, A.*; Boulyga, S.*; Kilburn, M.*

no journal, , 

Oral presentation

Safe and rapid analytical methods for actinide ions and radioactive Sr-90 in high-dose radiation samples using fluorescent probes in capillary electrophoresis

Haraga, Tomoko; Nakano, Yuta*; Sato, Yoshiyuki; Ouchi, Kazuki*; Hirose, Kazuki*; Shibukawa, Masami*; Ishimori, Kenichiro; Kameo, Yutaka; Saito, Shingo*

no journal, , 

no abstracts in English

36 (Records 1-20 displayed on this page)