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論文

Development of laser instrumentation devices for inner wall of high temperature piping system

西村 昭彦; 古澤 彰憲; 竹仲 佑介*

AIP Conference Proceedings 2033, p.080002_1 - 080002_5, 2018/11

 被引用回数:1 パーセンタイル:46.75(Green & Sustainable Science & Technology)

伝熱管内壁の検査補修技術として光ファイバイメージスコープとレーザー溶接技術を組み合わせた保守保全装置の開発を行ってきた。ファイバスコープによる観察、レーザー肉盛り加工補修、コノプローブ計測など主要な技術について報告する。本技術は高速炉配管への適用を計画している。本会議では、高速炉2次系配管と構造的に共通要素が多い太陽熱発電プラントへの適用を提案する。本技術は、高繰り返し熱負荷と溶融塩腐食にさらされる太陽熱発電プラントの保守保全に有用である。

論文

Leaching of radionuclides from a cement composite incorporating evaporator concentrate generated at a pressurized water reactor nuclear power plant

松鶴 秀夫; 森山 昇

Nuclear Science and Engineering, 80(1), p.14 - 25, 1982/00

 被引用回数:7 パーセンタイル:61.51(Nuclear Science & Technology)

PWR蒸発缶濃縮廃液のセメント固化体からの$$^{3}$$H,$$^{1}$$$$^{3}$$$$^{7}$$Cs,$$^{9}$$$$^{0}$$Sr,$$^{6}$$$$^{0}$$Coおよび$$^{1}$$$$^{4}$$$$^{4}$$Ceの水相への浸出を調べた。これらの核種の浸出速度は$$^{3}$$H$$>$$$$^{1}$$$$^{3}$$$$^{7}$$Cs$$>$$$$^{9}$$$$^{0}$$Sr$$>$$$$^{6}$$$$^{0}$$Co$$>$$$$^{1}$$$$^{4}$$$$^{4}$$Ceの順で大きく、その浸出性はセメント固化体中の廃棄物の量、浸出液の温度および硬化時間等に依存する。これらの結果から、最適固化条件を選ぶとともに、固化体の長期浸出性の推定を行った。

論文

Improvement of bitumen-waste product in leachability; -Leachability of bitumen product containing BWR's evaporator concentrates

森山 昇; 松鶴 秀夫; 土尻 滋

Annals of Nuclear Energy, 8(8), p.363 - 369, 1981/00

 被引用回数:0 パーセンタイル:0.00(Nuclear Science & Technology)

BWRで発生する濃縮廃液のビチューメン固化体の浸出性を改善するため、廃液に塩化カルシウムを添加して固化する方法を検討した。その結果、得られた固化体はほとんど膨潤が見られず、また$$^{1}$$$$^{3}$$$$^{7}$$Csと$$^{6}$$$$^{0}$$Coの浸出比は100日間でそれぞれ5$$times$$10$$^{-}$$$$^{4}$$および1$$times$$10$$^{-}$$$$^{4}$$となり、塩化カルシウムを添加しない固化体の場合にくらべて、極めて低い値を示した。さらに表面を5mm厚のビチューメンで被覆した固化体では、浸出液にほとんど放射能が検出されなかった。

論文

放射性廃液中のストロンチウム-90および全アルファ放射能の分析

藤崎 説男

京都大学原子炉実験所放射性廃棄物管理専門研究会報告書, p.20 - 25, 1981/00

東海研究所廃棄物処理場においては、国内及び国際的に定められている規則、指針に基ずいて処理用均一セメントパッケージ(以下、投棄物と記す。)の製作を行っている。これらの投棄物中に含まれる放射能は、固化前に廃液中の$$^{3}$$H、$$^{9}$$$$^{0}$$Sr、$$alpha$$核種、$$gamma$$核種を測定し、測定値の合計で評価を行っている。これらの測定法のうち、化学分析を伴う$$^{9}$$$$^{0}$$Sr及び$$alpha$$核種の放射能測定法についてのべる。ストロンチウムの分析は、基本的には科学技術庁編の「ストロンチウム分析法」に基づいている。廃液中に含まれる$$^{8}$$$$^{9}$$Srが$$^{9}$$$$^{0}$$Srの放射能にくらべ低く、分析誤差内であるために$$^{8}$$$$^{9}$$Srが$$^{9}$$$$^{0}$$Srの放射能の合計を$$^{9}$$$$^{0}$$Srの放射能として評価している。全アルファ放射能の分析は、試料を完全溶触したあと、アクチノイドを硫酸バリウムに共沈させ、蒸発乾固したものをガスフロー型の比例計数管で計測する方法である。これらの分析法は、再現性もよく、簡易分析法としては極めて優れた分析方法といえる。

口頭

Analysis of impurities in uranium ore concentrates using hand-held Raman spectroscopy

西脇 大貴; 木村 祥紀; 山口 知輝

no journal, , 

The spectra of seven types of industrially produced uranium ore concentrates were obtained using a hand-held Raman spectrometer. From the Raman spectra of several ammonium diuranates, the peak in the range of 806-827 cm$$^{-1}$$ and around 10$$^{10}$$ cm$$^{-1}$$ were identified uranyl ions and sulfate. The sulfates were impurities derived from the acid used in the manufacturing process. No significant differences were observed in the Raman spectra of two ammonium diuranatse samples made from ore or seawater. Thus, the Raman spectra measured by the hand-held type were more strongly influenced by the manufacturing process than the property of raw material.

口頭

Development of solidification techniques with minimised water content for secondary radioactive aqueous wastes in Fukushima, 6; Incorporation of simulated secondary aqueous wastes in CAC and CAP cements

Garc$'i$a-Lodeiro, I.*; Lebon, R.*; Mahoney, D.*; Zhang, B.*; 入澤 啓太; 大杉 武史; 中澤 修; 木下 肇*

no journal, , 

Incorporation of simulated aqueous secondary wastes in CAC and CAP cements was studied. The inclusion of simulated secondary wastes did not disturb the fundamental reaction of the systems, but the significant salt contents resulted in Friedel's salt in CAC and chlorapatite in CAP.

口頭

Investigation of the effectiveness of optical color measurement for screening UOC samples in nuclear forensics analysis

木村 祥紀; Shollenberger, Q. R.*; 松本 哲也*; Lindvall, R.*; Hoffman, D. C.*; 山口 知輝

no journal, , 

Uranium ores and uranium ore concentrates (UOCs) serve as front-end materials in the nuclear fuel cycle and exhibit distinct material characteristics, known as nuclear forensic signatures, which can assist in determining their origins such as the provenance and deposits. The interpretation of these signatures is often challenging due to the diversity of mining techniques and the complex nature of natural minerals. As part of a joint research collaboration between the Japan Atomic Energy Agency (JAEA) and the Nuclear Smuggling Detection and Deterrence (NSDD) program of NNSA/US DOE, we investigated nuclear forensic signatures and methodologies for tracing the origins of uranium-bearing materials, including ores and UOCs. This study focuses on the optical color measurement of UOCs as a potential screening method for identifying their chemical compounds. UOCs are known to exhibit a variety of colors, influenced by the oxidation states of uranium compounds and the presence of trace elements. Optical colors of seven UOC samples provided by JAEA were analyzed using different approaches by LLNL and JAEA. We will discuss the relationship between the optical colors of UOCs and their major uranium compounds as well as trace elements. The findings highlight the potential of optical color measurements as a screening tool to support nuclear forensic analysis and provide insights into the chemical diversity of UOCs.

口頭

US-Japan nuclear forensics analysis to identify the origins and process history of UOCs

Shollenberger, Q. R.*; 木村 祥紀; Inglis, J. D.*; Lindvall, R.*; 西脇 大貴; 山中 澪奈; 海野 勇次*; 細井 雅春*; Marks, N.*; Kips, R.*; et al.

no journal, , 

Uranium ore concentrate (UOC), or yellowcake, is a precursor material for nuclear fuel and is formed when uranium ore has been mined and milled (chemically processed). UOC is a commercially and internationally traded product, and several cases have been reported where UOC was found outside regulatory control or interdicted as part of a law enforcement investigation. Consequently, we need to advance our understanding of nuclear forensic signatures to identify the origins and process history of UOCs. Such signatures include the concentration of uranium (U), other minor and trace-level constituents, and isotopic composition of U or strontium (Sr). However, the interpretation of these nuclear forensic signatures can be difficult due to various types of uranium mining techniques, as well as the processing of U ores to UOCs. Therefore, multiple nuclear forensics signatures are necessary to determine material origin with high confidence. Through the Office of Nuclear Smuggling Detection and Deterrence (NNSA/US DOE/NSDD), we present the analysis of seven UOCs provided by the Japan Atomic Energy Agency (JAEA). Nuclear forensic measurements were performed on these UOCs at four different laboratories located in both the US and Japan. This study will focus on the signatures of uranium concentration, trace elements, and U and Sr isotopic compositions. We will discuss the results from the different laboratories and evaluate the importance of these signatures in the context of nuclear forensics.

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