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論文

Muon spin relaxation in mixed perovskite (LaAlO$$_3$$)$$_x$$(SrAl$$_{0.5}$$Ta$$_{0.5}$$O$$_3$$)$$_{1-x}$$ with $$xsimeq 0.3$$

伊藤 孝; 髭本 亘; 幸田 章宏*; 中村 惇平*; 下村 浩一郎*

Interactions (Internet), 245(1), p.25_1 - 25_7, 2024/12

We report on muon spin relaxation ($$mu^+$$SR) measurements in a mixed perovskite compound, (LaAlO$$_3$$)$$_{x}$$(SrAl$$_{0.5}$$Ta$$_{0.5}$$O$$_3$$)$$_{1-x}$$ with $$xsimeq 0.3$$ (LSAT), which is widely used as a single-crystalline substrate for thin film deposition. In zero applied field (ZF), muon depolarization due to the distribution of nuclear dipole fields was observed in the temperature range from 4 K to 270 K. Interestingly, $$mu^+$$SR time spectra in ZF maintained a Gaussian-like feature over the entire range, while the depolarization rate exhibited a monotonic decrease with increasing temperature. This behavior may be attributed to the thermally activated diffusion of muons between a few adjacent sites within a confined space of the angstrom scale, where the motionally averaged local field that each muon experiences can remain non-zero and result in maintaining the Gaussian-like line shape. The spatial distribution of electrostatic potential at lattice interstices evaluated via density functional theory calculations suggests that such a restriction of muon diffusion paths can be caused by the random distribution of cations with different nominal valences in the mixed perovskite lattice.

論文

Quantifying uncertainty induced by scattering angle distribution using maximum entropy method

丸山 修平; 山本 章夫*; 遠藤 知弘*

Annals of Nuclear Energy, 205, p.110591_1 - 110591_13, 2024/09

This study developed a new method for evaluating the uncertainty in reactor core/shielding characteristics attributable to the scattering angle distribution, employing a random sampling (RS) technique integrated with continuous energy Monte Carlo (CEMC) calculations. The impact of neutron scattering angle is not negligible in the analysis of fast reactor cores and shielding. Recent advancements have enabled the high-accuracy assessment of nuclear data-induced uncertainty by merging CEMC calculations and the RS technique. Nonetheless, a method to quantify uncertainty due to scattering angle distribution remains unestablished. This study introduces a new approach for uncertainty quantification related to scattering angle distribution in CEMC-RS, utilizing the maximum entropy method. The effectiveness of this method was verified through comparison with results from the classical deterministic uncertainty quantification approach based on generalized perturbation theory. Overall, this method offers a more accurate tool for nuclear engineers and researchers in evaluating and managing uncertainties in reactor design and safety analysis.

論文

High temperature nanoindentation of (U,Ce)O$$_{2}$$ compounds

Frazer, D.*; Saleh, T. A.*; 松本 卓; 廣岡 瞬; 加藤 正人; McClellan, K.*; White, J. T.*

Nuclear Engineering and Design, 423, p.113136_1 - 113136_7, 2024/07

ナノインデンテーション法では、微小な試験片を用いてヤング率,硬度及びクリープ強度といった機械物性を評価することが可能である。本研究ではMOX燃料の代替物質として(U,Ce)O$$_{2}$$を用いて、高温ナノインデンテーション試験を実施した。試料のCe含有率は0.1、0.2及び0.3mol%とし、温度は800$$^{circ}$$Cまでの測定を行い、ヤング率、硬度及びクリープ強度の評価を行った。温度の上昇に伴い、ヤング率は線形的に低下し、硬度は指数関数的に低下する結果が得られた。また、800$$^{circ}$$Cにおいては、応力指数n=4.7$$sim$$6.9のクリープ変形が得られた。

論文

Quantitative analysis of microstructure evolution, stress partitioning and thermodynamics in the dynamic transformation of Fe-14Ni alloy

Li, L.*; 宮本 吾郎*; Zhang, Y.*; Li, M.*; 諸岡 聡; 及川 勝成*; 友田 陽*; 古原 忠*

Journal of Materials Science & Technology, 184, p.221 - 234, 2024/06

 被引用回数:0 パーセンタイル:0(Materials Science, Multidisciplinary)

Dynamic transformation (DT) of austenite ($$gamma$$) to ferrite ($$alpha$$) in the hot deformation of various carbon steels was widely investigated. However, the nature of DT remains unclear due to the lack of quantitative analysis of stress partitioning between two phases and the uncertainty of local distribution of substitutional elements at the interface in multi-component carbon steels used in the previous studies. Therefore, in the present study, a binary Fe-Ni alloy with $$alpha$$+$$gamma$$ duplex microstructure in equilibrium was prepared and isothermally compressed in $$alpha$$+$$gamma$$ two-phase region to achieve quantitative analysis of microstructure evolution, stress partitioning and thermodynamics during DT. $$gamma$$ to $$alpha$$ DT during isothermal compression and $$alpha$$ to $$gamma$$ reverse transformation on isothermal annealing under unloaded condition after deformation were accompanied by Ni partitioning. The lattice strains during thermomechanical processing were obtained via in-situ neutron diffraction measurement, based on which the stress partitioning behavior between $$gamma$$ and $$alpha$$ was discussed by using the generalized Hooke's law. A thermodynamic framework for the isothermal deformation in solids was established based on the basic laws of thermodynamics, and it was shown that the total Helmholtz free energy change in the deformable material during the isothermal process should be smaller than the work done to the deformable material. Under the present thermodynamic framework, the microstructure evolution in the isothermal compression of Fe-14Ni alloy was well explained by considering the changes in chemical free energy, plastic and elastic energies and the work done to the material. In addition, the stabilization of the soft $$alpha$$ phase in Fe-14Ni alloy by deformation was rationalized since the $$gamma$$ to $$alpha$$ transformation decreased the total Helmholtz free energy by decreasing the elastic and dislocation energies.

論文

MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3

佐藤 一憲; 吉川 信治; 山下 拓哉; 下村 健太; Cibula, M.*; 溝上 伸也*

Nuclear Engineering and Design, 422, p.113088_1 - 113088_24, 2024/06

The accident progression of the in-vessel phase of Fukushima Daiichi Nuclear Power Station Unit 1 was analyzed using the MAAP code. Although there is a large uncertainty in the initial stage of accident progression behavior in Unit 1 with little measurement data, it is presumed to have similarities to that of Unit 3. As a result, in Unit 1, since there was almost no alternative water injection during the in-vessel phase, cooling of the debris transferred to the lower plenum was small. It was likely that a large molten pool of metals had formed, and that the steam supply to the high-temperature core materials was suppressed and metal oxidation was relatively small. The analysis results for Unit 1 were compared with those for Units 2 and 3, and differences between units such as the thermal conditions of the debris that relocated to the pedestal and the degree of metal oxidation were shown.

論文

Development of a radioactive substance detection system integrating a Compton camera and a LiDAR camera with a hexapod robot

佐藤 優樹; 角藤 壮*; 田中 孝幸*; 嶋野 寛之*; 諸橋 裕子; 畠山 知圭*; 中島 準作; 石山 正弘

Nuclear Instruments and Methods in Physics Research A, 1063, p.169300_1 - 169300_7, 2024/06

A system for locating radioactive substances using a hexapod robot equipped with a Compton camera and light detection and ranging camera was developed, and its performance evaluation test was conducted at FUGEN, a nuclear facility owned by Japan Atomic Energy Agency. In the test, by projecting images of radioactive substances acquired with the Compton camera onto a three-dimensional model of the work environment acquired with a light detection and ranging camera, the locations where radioactive substances have accumulated and the dose rate is higher than the surrounding area were successfully visualized and identified.

論文

Interaction of solute manganese and nickel atoms with dislocation loops in iron-based alloys irradiated with 2.8 MeV Fe ions at 400 $$^{circ}$$C

Nguyen, B. V. C.*; 村上 健太*; Chena, L.*; Phongsakorn, P. T.*; Chen, X.*; 橋本 貴司; Hwang, T.*; 古澤 彰憲; 鈴木 達也*

Nuclear Materials and Energy (Internet), 39, p.101639_1 - 101639_9, 2024/06

In reactor pressure vessel materials, the formation of Mn- and Ni-rich nanoclusters is a major cause of neutron irradiation embrittlement. The segregation of these solute atoms into dislocation loops has attracted attention as a mechanism to accelerate solute clustering. In this study, the behaviors of solute Mn and Ni atoms in Fe-0.6wt.%Ni, Fe-1.4wt.%Mn, and Fe-1.4wt.%Mn-0.6wt.%Ni alloys irradiated at 400 $$^{circ}$$C up to 3 dpa were analyzed using three-dimensional atom probe tomography. Solute atom clusters were observed in all materials, and their shapes were spherical, flat, and torus in FeNi, FeMn, and FeMnNi, respectively. In ternary alloy FeMnNi, Mn and Ni atoms were concentrated in the sample in the form of arcs, and the orientation of the plane containing the arcs was estimated by comparing field desorption images. The size, number density, and orientation of this structure were found to be in good agreement with those of both types of dislocation loops, namely, b = 1/2 $$<$$111$$>$$ and b = $$<$$100$$>$$, identified in a previous study using the same material. The positions of Ni and Mn enrichment did not fully overlap. Ni atoms tended to be concentrated more in the inner part of the loop than the Mn atoms. Mn atoms were enriched only in the vicinity of the dislocation loops, whereas Ni atoms showed a higher concentration inside the dislocation loops than in the bulk.

報告書

革新的水質浄化剤の開発による環境問題低減化技術の開拓(委託研究); 令和4年度英知を結集した原子力科学技術・人材育成推進事業

廃炉環境国際共同研究センター; 信州大学*

JAEA-Review 2023-053, 87 Pages, 2024/05

JAEA-Review-2023-053.pdf:4.67MB

日本原子力研究開発機構(JAEA)廃炉環境国際共同研究センター(CLADS)では、令和4年度英知を結集した原子力科学技術・人材育成推進事業(以下、「本事業」という)を実施している。本事業は、東京電力ホールディングス株式会社福島第一原子力発電所の廃炉等をはじめとした原子力分野の課題解決に貢献するため、国内外の英知を結集し、様々な分野の知見や経験を、従前の機関や分野の壁を越えて緊密に融合・連携させた基礎的・基盤的研究及び人材育成を推進することを目的としている。平成30年度の新規採択課題から実施主体を文部科学省からJAEAに移行することで、JAEAとアカデミアとの連携を強化し、廃炉に資する中長期的な研究開発・人材育成をより安定的かつ継続的に実施する体制を構築した。本研究は、令和2年度に採択された研究課題のうち、「革新的水質浄化剤の開発による環境問題低減化技術の開拓」の令和2年度から令和4年度分の研究成果について取りまとめたものである。本研究は、東日本大震災で発生した放射性汚染水の処理問題改善に資するため、吸着性能に優れ再利用可能なストロンチウムイオン用吸着剤の開発を目指した。その結果、ストロンチウムイオンに対して優れた吸着性能を有する、再利用可能な吸着材料の開発に成功した。現行のストロンチウム用吸着材料は、極めて高価であると共に使い捨てであるため、使用済み吸着剤の廃棄量は既に膨大となっており、それら廃棄物の保管や処分方法が大きな問題となっている。そのため、今回開発した吸着材料を実装化することで、これらの問題を大きく緩和することが期待できる。また、吸着材料は一般に粉体として得られるため、バインダーを利用してカラム通水による除染に適した粒径に造粒化する必要がある。これに対し、今回開発した材料は、最初から適した粒状物として得られるところに大きな特徴があり、煩雑な造粒化工程を省くことで、製造コストの削減も期待できる。これらの結果は当初の開発目標に合致したものであり、廃炉加速化に貢献できると考えられる。これらの研究は、研究代表者の下で各研究項目間並びに廃炉環境国際共同研究センター(CLADS)等との連携を密にして進めた。また、研究実施計画を推進するための打合せや会議等を開催した。

報告書

建屋応答モニタリングと損傷イメージング技術を活用したハイブリッド型の原子炉建屋長期健全性評価法の開発研究(委託研究); 令和4年度英知を結集した原子力科学技術・人材育成推進事業

廃炉環境国際共同研究センター; 東北大学*

JAEA-Review 2023-048, 151 Pages, 2024/05

JAEA-Review-2023-048.pdf:8.48MB

日本原子力研究開発機構(JAEA)廃炉環境国際共同研究センター(CLADS)では、英知を結集した原子力科学技術・人材育成推進事業を実施している。本事業は、東京電力ホールディングス福島第一原子力発電所の廃炉等をはじめとした原子力分野の課題解決に貢献するため、国内外の英知を結集し、様々な分野の知見や経験を、従前の機関や分野の壁を越えて緊密に融合・連携させた基礎的・基盤的研究及び人材育成を推進することを目的としている。本研究は、令和3年度に採択された研究課題のうち、「建屋応答モニタリングと損傷イメージング技術を活用したハイブリッド型の原子炉建屋長期健全性評価法の開発研究」の令和4年度分の研究成果について取りまとめたものである。

報告書

マイクロ波重畳LIBSによるデブリ組成計測の高度化と同位体の直接計測への挑戦(委託研究); 令和4年度英知を結集した原子力科学技術・人材育成推進事業

廃炉環境国際共同研究センター; アイラボ*

JAEA-Review 2023-029, 77 Pages, 2024/05

JAEA-Review-2023-029.pdf:3.98MB

日本原子力研究開発機構(JAEA)廃炉環境国際共同研究センター(CLADS)では、令和4年度英知を結集した原子力科学技術・人材育成推進事業(以下、「本事業」という。)を実施している。本事業は、東京電力ホールディングス株式会社福島第一原子力発電所の廃炉等をはじめとした原子力分野の課題解決に貢献するため、国内外の英知を結集し、様々な分野の知見や経験を、従前の機関や分野の壁を越えて緊密に融合・連携させた基礎的・基盤的研究及び人材育成を推進することを目的としている。平成30年度の新規採択課題から実施主体を文部科学省からJAEAに移行することで、JAEAとアカデミアとの連携を強化し、廃炉に資する中長期的な研究開発・人材育成をより安定的かつ継続的に実施する体制を構築した。本研究は、令和2年度に採択された研究課題のうち、「マイクロ波重畳LIBSによるデブリ組成計測の高度化と同位体の直接計測への挑戦」の令和2年度から令和4年度分の研究成果について取りまとめたものである。本研究は、MW(マイクロ波)重畳によりLIBS(レーザーブレークダウン分光)の発光強度を上げ、ウラン同位体計測に適用することを目的としている。令和4年度では、半導体マイクロ発振器をさらに小型化するために冷却方式の見直しや必須とならない機能の削減を行い、さらにマイクロ波アンテナにおいてはシミュレーションで得た最適化条件をLIBS実験に適用することにより良好な結果が得られた。同位体計測について、スペクトル調査を行い、同位体をもつウランとスペクトルが似ているジルコニウムでLIBS測定の最適化を行い、100倍以上の増倍率が得られた。さらに、テーブルトップLIBS光学系、小型化されたLIBSセンサー部、マイクロ波アンテナの統合とシステムの評価を行い、ステンレス(Cr含有)・Pb・Al等を用いて計測性の向上効果を検討したところ、材料によらずマイクロ波重畳によるシグナル強度の増大効果・SN比向上の効果が出ることが分かった。MW重畳有り/無しのLIBSスペクトルの差異を検討し、スペクトラムの差異、データ処理の仕様を決定し、ビーム検出精度を向上するパラメータ抽出が可能となった。ピーク検出と背景光のデータ解析ソフトウェアの構築を開始した。最終年度である本年の最後に、目的とするウランの同位体計測を行った。マイクロ波による増強効果が得られ、マイクロ波重畳LIBSの計測は成功した。

報告書

Analysis of the relationship between operational quantity used for area monitoring and protection quantity for external exposure

遠藤 章

JAEA-Research 2024-002, 90 Pages, 2024/05

JAEA-Research-2024-002.pdf:4.22MB

本報告書は、光子、中性子、電子、陽電子、陽子、ミューオン、パイ中間子及びヘリウムイオンによる外部被ばくについて、エリアモニタリングに用いられる3つの量である周辺線量当量$$H^*$$(10)、最大線量当量$$H^*_textrm{max}$$及び周辺線量$$H$$$$^{*}$$と実効線量との関係を包括的に分析した結果を示す。分析のための計算は、PHITS (Particle and Heavy Ion Transport code System)とICRU球を用いて行った。その結果、ICRP Publication 116で対象としている幅広いエネルギー範囲における外部被ばくに対して、$$H^*$$(10)と$$H^*_textrm{max}$$は実効線量の評価に大きな差を生じる場合がある一方、$$H$$$$^{*}$$はエリアモニタリングに許容される範囲で実効線量を保守的に評価できることが分かった。すなわち、実効線量を評価するために、$$H^*$$(10)と$$H^*_textrm{max}$$には限界があり、より適切な量として$$H$$$$^{*}$$の使用が推奨される。この結論は、多様な被ばく状況における実効線量の評価に$$H$$$$^{*}$$を導入したICRU Report 95の提案を支持するものである。周辺線量$$H$$$$^{*}$$の利用は、医療や学術研究における放射線利用や航空機搭乗時の被ばく等の様々な種類の放射線により被ばくする状況で特に重要であり、放射線防護の対象の拡大に伴う放射線モニタリングの新たなニーズに応えることができる。

論文

Experimental investigation on local flow structures of upward cap-bubbly flows in a vertical large-size square channel

孫 昊旻; 功刀 資彰*; 横峯 健彦*; Shen, X.*; 日引 俊*

Experimental Thermal and Fluid Science, 154, p.111171_1 - 111171_24, 2024/05

 被引用回数:0

Taking the importance of gas-liquid two-phase flows in large square channels for advanced nuclear reactors, such as ESBWR, we experimented with upward cap-bubbly flows in a large square channel. Local void fractions, axial gas velocities, and interfacial area concentrations for two bubble-size groups were measured at three axial locations. Based on the database, cap-bubbly flow characteristics in a large square channel were understood. The existing drift-flux and interfacial area concentration correlations were validated. The void fraction covariances were obtained and used to validate their existing correlations.

論文

"Invisible" radioactive cesium atoms revealed; Pollucite inclusion in cesium-rich microparticles (CsMPs) from the Fukushima Daiichi Nuclear Power Plant

宮崎 加奈子*; 武原 政人*; 蓑毛 健太*; 堀江 憲路*; 竹原 真美*; 山崎 信哉*; 斉藤 拓巳*; 大貫 敏彦*; 高野 公秀; 塩津 弘之; et al.

Journal of Hazardous Materials, 470(15), p.134104_1 - 134104_11, 2024/05

Radioactive Cs contamination has been one of the central issues in Fukushima and other legacy sites; however, atomic-scale characterization of radioactive Cs has never been successful. Here we report, for the first time, the direct imaging of radioactive Cs atoms using high-resolution high-angle annular dark-field scanning transmission electron microscopy. As inclusions in Cs-rich microparticles, 27-36 wt.% of Cs (as Cs$$_{2}$$O) occurs in a type of zeolite called pollucite. The normalized formula for pollucite are expressed as (Cs,K,Ba)$$_{2.2}$$(Fe$$_{0.84}$$,Zn$$_{0.84}$$,X$$_{0.5}$$)$$_{2.2}$$Si$$_{4.1}$$O$$_{12}$$, (Cs,K,Ba)$$_{1.5}$$(Fe$$_{0.66}$$Zn$$_{0.32}$$X$$_{0.6}$$)$$_{1.6}$$Si$$_{4.6}$$O$$_{12}$$, and (Cs,K,Ba)$$_{1.7}$$(Fe$$_{0.60}$$Zn$$_{0.32}$$X$$_{1.0}$$)$$_{1.9}$$Si$$_{4.4}$$O$$_{12}$$ after normalization with 12 oxygen atoms (X includes other trace cations; Ti, Mn, Rb, Zr, Mo, and Sn). Atomic-resolution image of radioactive Cs atoms are obtained when viewing along the [111] zone axis, a view supported by image simulations using the multi-slice method. The occurrence of pollucite indicates that locally enriched Cs reacted with siliceous substances during meltdowns, presumably through hydrothermal reactions. In case of predominant occurrence of pollucite in debris, incorporation in pollucite structure retards leaching of radioactive Cs. Still, the atomic-resolution imaging of radioactive Cs is an important advance for better understanding the fate of radioactive Cs inside and outside of damaged reactors during severe accidents like Fukushima Daiichi.

論文

Organization of malonamides from the interface to the organic bulk phase

Micheau, C.; 上田 祐生; 元川 竜平; 阿久津 和宏*; 山田 悟史*; 山田 雅子*; Moussaoui, S. A.*; Makombe, E.*; Meyer, D.*; Berthon, L.*; et al.

Journal of Molecular Liquids, 401, p.124372_1 - 124372_12, 2024/05

Supramolecular organization of extractant molecules impacts metal ions separation behavior. Probing bulk and interfacial structures of the relevant systems is expected to provide key insights into the metal ion selectivity and kinetic aspects. The supramolecular features of two solvent extraction systems based on malonamide extractants, N,N,N′,N′-tetrahexylmalonamide (THMA) in toluene and N,N′-dimethyl-N,N′-dibutyl-2-tetradecylmalonamide (DBMA) in n-heptane, were studied using small-angle X-ray scattering for the organic bulk phases, as well as interfacial tension and neutron reflectivity measurements for the interfaces. In the bulk solution, THMA forms dimeric/trimeric associates but no aggregates in toluene, while DBMA forms large aggregates in n-heptane. On the other hand, THMA accumulates in a diffuse layer at the interface at high THMA concentration, whereas DBMA forms a compact but thinner layer. After Pd(II) extraction, the thickness of interfacial layers decreases in the case of THMA, and totally vanishes in the case of DBMA. Based on these new structural information, two mechanisms are proposed for Pd(II) and Nd(III) extraction with malonamides. In toluene, THMA associates slightly accumulate in the vicinity of the interface, then coordinate Pd(II) and diffuse into the organic bulk phase. In n-heptane, DBMA aggregates adsorb at the interface then pick up Nd(III) cations in their polar cores and finally diffuse into the bulk.

論文

A Science-based mixed oxide property model for developing advanced oxide nuclear fuels

加藤 正人; 沖 拓海; 渡部 雅; 廣岡 瞬; Vauchy, R.; 小澤 隆之; 上羽 智之; 生澤 佳久; 中村 博樹; 町田 昌彦

Journal of the American Ceramic Society, 107(5), p.2998 - 3011, 2024/05

 被引用回数:0 パーセンタイル:0.01(Materials Science, Ceramics)

Herein, a science-based uranium and plutonium mixed oxide (MOX) property model (Sci-M Pro) is derived for determining properties of MOX fuel and analyzing their performance as functions of Pu content, minor-actinide content, oxygen-to-metal ratio, and temperature. The property model is constructed by evaluating the effect of phonons and electronic defects on heat capacity and thermal conductivity of MOX fuels. The effect of phonons was evaluated based on experimental datasets related to lattice parameter, thermal expansion, and sound speeds. Moreover, the effect of electronic defects was determined by analyzing oxygen-potential data based on defect chemistry. Furthermore, the model evaluated the effect of the Bredig transition on the thermal properties of MOX fuel by analyzing the irradiation test results. The derived property model is applied to the performance code to analyze fast reactor fuel pins.

論文

Investigation of sorption behavior of $$^{137}$$Cs in a river-sea system boundary area after the Fukushima Dai-ichi Nuclear Power Plant accident

高田 兵衛*; 脇山 義史*; 和田 敏裕*; 平尾 茂一*; 青野 辰雄*; 中西 貴宏; 御園生 敏治; 尻引 武彦; 青山 道夫*

Marine Chemistry, 262, p.104384_1 - 104384_6, 2024/05

The radiocesium ($$^{137}$$Cs) distribution between dissolved and particulate phases was examined in river water and coastal seawater as a function of the $$^{137}$$Cs sorption behavior on suspended particles. Dissolved $$^{137}$$Cs activity concentrations in the Tomioka River (salinity $$<$$ 0.1) and in coastal seawater at Tomioka fishery port (salinity $$>$$ 30), Fukushima Prefecture, from June 2019 to October 2021 were 3.6-20 Bq/m$$^{3}$$ (geometric mean 11 Bq/m$$^{3}$$) and 2.4-86 Bq/m$$^{3}$$ (13 Bq/m$$^{3}$$), respectively. Although the suspended particle concentration was lower in the river (0.2-44 mg/L; geometric mean 2 mg/L) than in seawater (0.8-24 mg/L; 6.4 mg/L), the mean $$^{137}$$Cs activity on suspended particles was 11,000 Bq/kg-dry in the river versus 3,200 Bq/kg-dry in seawater. Proportions of ion-exchangeable, organically bound, and refractory fractions of $$^{137}$$Cs on suspended particles were determined by sequential extraction. The ion-exchangeable fraction accounted for 0.3-2.0% (mean 1.2%) and 0.4-1.3% (0.8%) at the river and port sites, respectively. The organically bound fraction accounted for 0.3-4.8% (1.8%) and 0.1-5.5% (2.1%) at the river and port sites, respectively. In both areas, the refractory fraction accounted for $$>$$ 90% of $$^{137}$$Cs. Unexpectedly, the ion-exchangeable fraction did not differ between the river and port sites, and the percentage at the river site did not vary during the sampling period. Therefore, the ion-exchangeable fraction in the river's lower reach was originally low or had decreased before the particles arrived there. The small labile $$^{137}$$Cs fraction on suspended particles indicates that the mobility of radiocesium to marine biota in this coastal region is low.

論文

Mechanical stability of retained austenite and texture evolution in additively manufactured stainless steel

Chae, H.*; Huang, E.-W.*; Jain, J.*; Lee, D.-H.*; Harjo, S.; 川崎 卓郎; Lee, S. Y.*

Metals and Materials International, 30(5), p.1321 - 1330, 2024/05

In situ neutron diffraction during tensile deformation was performed for the stainless steels prepared by the additive manufacturing (AM) processes with two strategies: vertically built and horizontally built. The AM steels were further aged without solid solution treatment. As the results, the retained austenite was found to be more stable because the chemical composition became homogeneous by aging, and the onset of deformation induced martensitic transformation was delayed.

論文

First demonstration of a single-end readout position-sensitive optical fiber radiation sensor inside the Fukushima Daiichi Nuclear Power Station based on wavelength-resolving analysis

寺阪 祐太; 佐藤 優樹; 瓜谷 章*

Nuclear Instruments and Methods in Physics Research A, 1062, p.169227_1 - 169227_6, 2024/05

We have developed a new position-sensitive optical fiber radiation sensor that achieves single-end readout and high dose rate application. The sensor determines the incident position of radiation on the optical fiber by using the wavelength dependency of light attenuation within the fiber. Through the analysis of the output wavelength spectrum from the fiber end, the incident position of radiation on the optical fiber can be inversely estimated using the spectrum unfolding procedure. Using this optical fiber sensor, we conducted a measurement of radiation distribution inside the Fukushima Daiichi Nuclear Power Station (FDNPS). The actual trend of incident position of radiation was successfully reproduced in a high dose rate area, with a maximum dose rate exceeding 100 mSv/h. This validates the effectiveness of our new position-sensitive optical fiber radiation sensor.

論文

Development of a practical tritiated water monitor to supervise the discharge of treated water from Fukushima Daiichi Nuclear Power Plant

眞田 幸尚; 押切 圭介*; 菅野 麻里奈*; 阿部 智久

Nuclear Instruments and Methods in Physics Research A, 1062, p.169208_1 - 169208_7, 2024/05

福島第一原子力発電所(FDNPP)の廃炉作業の一環として、2023年から貯蔵処理水の放出が開始される。本研究では、FDNPPでのバッチサンプリング測定により確認されたトリチウム水の濃度を連続的に監視する実用的なトリチウムモニタを開発した。このモニターは、安価なプラスチックシンチレータペレットからなるフローセル検出器を配置し、3つの検出器による同時測定、ベト検出器、環境$$gamma$$線の影響を低減するための鉛遮蔽を組み込んだ。このシステムは、測定時間30分で911Bq L-1の検出限界に達し、これはトリチウム水の排出基準1,500Bq L-1よりも低い。このシステムはまた、$$beta$$線スペクトルを用いて、トリチウム以外の妨害放射性核種やバックグラウンド放射線による妨害の存在を定性的に区別することができる。また、$$beta$$線スペクトルを用いて、トリチウム以外の妨害放射性核種やバックグラウンド放射線による妨害の有無を定性的に区別することができる。

論文

Archie's cementation factors for natural rocks; Measurements and insights from diagenetic perspectives

Yuan, X.*; Hu, Q. H.*; Fang, X.*; Wang, Q. M.*; Ma, Y.*; 舘 幸男

Sedimentary Geology, 465, p.106633_1 - 106633_14, 2024/05

Archie's cementation factor, m, is a critical parameter for petrophysical studies, and the value is influenced by several factors such as the shape, type, and size of grains, degrees of diagenesis, and associated pore structure. Using integrated experimental and theoretical approaches, the goal of this study is to obtain the cementation factor of rocks (both reservoir rock and caprock) and assess the impact of diagenesis processes on the values of the cementation factor. Thirteen samples of geologically diverse rocks (six mudstones, four fossiliferous limestones, two marbles, and one sandstone) were selected to achieve these research objectives. Two approaches, the diffusion of gas tracers and the Bosanquet formula calculation using pore-throat sizes from mercury intrusion porosimetry analyses, were used to derive the cementation factors of these rock samples. These rocks were categorized into two groups based on the correlation between average pore-throat diameter and diffusivity, and an exponential-law relationship between the cementation factor and porosity was determined for these sample groups. In addition, thin-section petrography and field emission-scanning electron microscopy observations were utilized to investigate diagenetic processes, with four diagenetic patterns being established: (1) strong compaction, strong cementation, and weak dissolution-diagenesis pattern; (2) weak compaction, medium cementation, and weak dissolution-diagenesis pattern; (3) weak compaction, medium cementation, and strong dissolution-diagenesis pattern; and (4) fracture-matrix pattern. The results indicated that diagenetic processes and microfractures contribute to the variability in the cementation factors in these rock samples.

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