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荒井 陽一; 長谷川 健太; 渡部 創; 渡部 雅之; 箕輪 一希*; 松浦 治明*; 羽倉 尚人*; 勝木 健太*; 新井 剛*; 小西 康裕*
Journal of Radioanalytical and Nuclear Chemistry, 9 Pages, 2023/00
被引用回数：0 パーセンタイル：0.01(Chemistry, Analytical)Radioactive aqueous and organic liquid wastes contaminated by U are generated by solvent extraction of nuclear fuel materials in experiments of reprocessing technologies. Although incineration and denitrification/conversion processes are promising for treating such liquid waste, the installation of large equipment is essential. To give appropriate treatment procedures for radioactive liquid waste generated in nuclear facilities, STRAD (Systematic Treatments of RAdioactive liquid wastes for Decommissioning) project was started by Japan Atomic Energy Agency (JAEA) with several organizations. We are focusing on baker's yeasts for their excellent metal ions adsorption characteristics, easy handling and low prices. In order to optimize adsorption performance and operation procedures as the liquid waste treatment technology, adsorption performance of U has to be precisely investigated. In this study, adsorption performance of U and anion from nitric acid solution was investigated by batch-wise adsorption experiments.
松井 芳樹; 木村 祥紀; 海野 勇次*; 細井 雅春*; 松本 哲也*; 篠原 伸夫; 山崎 斉; 山口 知輝
no journal, ,
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the JAEA is developing technologies for nuclear forensics to identify the origin and intended use of nuclear and radioactive materials. The Nuclear Forensics International Technical Working Group (ITWG) regularly holds the Collaborative Materials Exercise (CMX) to share the experience on nuclear forensics analysis and to improve analytical methods in the international community. The ISCN participated in the 7th exercise (CMX-7) this time. This paper discusses the experience of the ISCN during the CMX-7 including the results of laboratory analysis and nuclear forensics interpretation, as well as future challenges for laboratory capability at the ISCN. In the CMX-7, under the hypothetical case scenario (illegal transferring of nuclear materials), uranium samples and other conventional forensics evidence were provided for the exercise. During the exercise, participants reported the analytical results according to the timeframes recommended by the Nuclear Forensics Guidelines of the IAEA (24 hours, 1 week, and 2 months from sample receipt). The ISCN reported the physical characteristics and the results NDA analysis on the uranium samples at the first two timeframes, and the results of mass spectrometry with the data interpretation as the 2 months report. The results of uranium isotope ratio and trace elements measurements were exceedingly good, but the results of age dating were significantly deviate from the overall average. Reducing the time for destructive analysis that allows timely provisions of the results, as well as the improvement of the confidence in age dating are future tasks for the nuclear forensics analysis of the ISCN laboratory.
松枝 誠; 川上 智彦*; 照山 優子*; 寺島 元基; 飯島 和毅; 古川 真*; 高貝 慶隆*
no journal, ,
アクチノイドは、高エネルギーの
線を放出することから、内部被ばくリスクが高い放射性物質であるため、原子力発電所や放射性廃棄物の安全管理上、その分析は重要となる。従来から利用されてきた線スペクトロメトリーによる分析方法では、多段階の前処理が必要であり、時間もかかるといった問題があった。誘導結合プラズマ質量分析法(ICP-MS)は、様々な自動前処理装置を組み合わせることで、前処理工程を省略し、迅速かつ簡便な分析法を実現する可能性を持つ。また、前処理装置との組合せは、ICP-MSを用いたアクチノイドの同時定量を実現する可能性を拡げることも可能である。本研究では、アクチノイド(Th, U, Pu, Am)の同時定量に向けた、全自動オンライン固相抽出(SPE)-ICP-MSシステムを開発した。
Bujak, R.*; 佐藤 義行; Katona, R.*; Konegger-Kappel, S.*; Koepf, A.*; Boulyga, S.*; Kilburn, M.*
no journal, ,
The environmental sampling program of the International Atomic Energy Agency serves to assess the completeness of State's declaration of the nuclear fuel cycle. Nuclear signatures that are collected on cotton swipes bear valuable information that help to draw safeguards conclusions. There is an increasing need to provide information on the age of Pu material by measuring Pu-241 and its daughter isotope Am-241, hence the Environmental Sample Laboratory (ESL) is extending its analytical capabilities to determine Am-241 down to the fg level. Since the goal of the work was to apply the new procedure to very small quantities of Pu and Am, and also to explore the limitations associated with chemical sample preparation and mass spectrometric analysis, test materials were prepared with 6 - 12 fg Am-241 and 0.6 - 1.2 fg Pu-241. All tested methods satisfactorily removed the REE to below one ppb. The calculated age of the CRM 137 agreed with the consensus value within uncertainties, whereas the expanded uncertainty (k=2) of the age varied between 4 and 4.5 years due to the very low amounts of Am and Pu analyzed.
