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)
(SrAl
TaO)
with 
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 (
SR) measurements in a mixed perovskite compound, (LaAlO)
(SrAlTaO) with (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, 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.
SR studies on copper minerals藤原 理賀; 岡部 博孝*; 幸田 章宏*
Interactions (Internet), 245(1), p.13_1 - 13_6, 2024/12
量子状態を実験的に観測することは難しい。さらに、エキゾチックな量子状態が実現すると予測されている格子系の中には、理想的なモデル物質が見つかっていない系も存在する。銅鉱物の中には、未研究の低次元量子磁性体がまだまだ多く存在し、その数は年々増加している。我々は、銅鉱物が発見された自然環境を模倣することで7種類の銅鉱物の人工合成に成功し、さらにその量子状態を報告した。パルスミュオンの特性は、人工銅鉱物のスピン状態の調査に大変適している。その有用性を、fedotoviteのSR測定の結果を示しながら、紹介する。
安部 諭; 柴本 泰照
Annals of Nuclear Energy, 202, p.110461_1 - 110461_16, 2024/07
During a severe accident in a nuclear containment vessel, jets released from the primary system exhibit complex thermohydraulic behavior due to buoyancy effects and impingement on internal obstacles such as inner walls and floors. Thus, the obstacle-influenced jets are of interest in recent research activities. This paper describes an experimental investigation of the behavior of jets passing through a grid-type obstacle. The flow field was acquired by a particle image velocimetry system. The experiment captured the jet fragmentation by the grid-type obstacle and their recoupling. The mean velocity field obtained by postprocessing indicates a "Rectifying effect," with the axial velocity increasing at the center and the magnitude of the radial velocity decreasing. The meandering flow was suppressed due to this effect. In the near grid-obstacle region, the axial turbulence intensity was relatively large at the edge of each fragmented region due to shear stress. Moreover, the spatial distribution of the radial turbulence fluctuation became more complex. Further investigation is required to clarify the budget of the transport equation for turbulence fluctuation. The experimental data shown in this paper is useful for computational fluid dynamics validation.
Pu
O
powder using master sintering curve theory中道 晋哉; 砂押 剛雄*; 廣岡 瞬; Vauchy, R.; 村上 龍敏
Journal of Nuclear Materials, 595, p.155072_1 - 155072_11, 2024/07
Using dry recycled powders for uranium and plutonium mixed oxide (MOX) fuel production can reduce unnecessary storage and accountability of nuclear material in facilities. The shrinkage behavior of green compacts of dry recycled powders differs from that of conventional raw powders because the dry recycled MOX powder is obtained from the fabrication scrap of sintered pellets. The shrinkage behavior of dry recycled MOX powder has been investigated by dilatometry. Based on the shrinkage curves, sintering apparent activation energies were evaluated using the master sintering curve (MSC) and the constant rate of heating methods. The obtained values were higher than the energy evaluated for raw powder experiments. The sigmoid sintering prediction equation using the MSC function was constructed. The accumulation of data on the activation energy for various sintering conditions will lead to the wide application of this prediction formula in the future.
compoundsFrazer, 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
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、800Cにおいては、応力指数n=4.7
6.9のクリープ変形が得られた。
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 (
) to ferrite (
) 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 + duplex microstructure in equilibrium was prepared and isothermally compressed in + two-phase region to achieve quantitative analysis of microstructure evolution, stress partitioning and thermodynamics during DT. to DT during isothermal compression and to 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 and 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 phase in Fe-14Ni alloy by deformation was rationalized since the to transformation decreased the total Helmholtz free energy by decreasing the elastic and dislocation energies.
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.
CNguyen, 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 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.
C powder and BC pellet regarding the eutectic reaction with stainless steelHong, Z.*; Ahmed, Z.*; Pellegrini, M.*; 山野 秀将; Erkan, N.*; Sharma, A. K.*; 岡本 孝司*
Progress in Nuclear Energy, 171, p.105160_1 - 105160_13, 2024/06
本研究では、BC粉末とステンレス鋼(SS)間との共晶反応はBC粉ペレットとSS間とのそれより相当に速いことが分かった。粉末及びペレットに対して導出された反応速度定数は参考文献値によく一致している。また、粉末とペレットの場合の詳細微細構造をSEM/EDSを用いて組成分析を行った。粉末の場合、(Fe,Cr)Bからなる反応層として厚肉層が見られた。一方、ペレットの場合、2つの反応層が見られた。
迫田 晃弘; 石森 有; Jin, Q.*; 飯本 武志*
Applied Radiation and Isotopes, 207, p.111180_1 - 111180_8, 2024/05
建物内壁のラドン(
Rn)及びトロン(
Rn)散逸率のin-situ測定におけるデータ解析技術の向上を目的に、解析で用いる数理モデルと関連パラメータの影響を調べた。その結果、測定系内の放射能濃度の不均一性を考慮すべきなのは、ラドンよりもトロンの場合であることがわかった。また、解析結果の品質をより向上させるために、屋内ラドンの日内変動を解析で考慮すべきであることがわかった。散逸率測定の目的と要求精度の下で、適切なモデルを作成・選択する必要があることが示された。
田中 万也; 山路 恵子*; 升屋 勇人*; 富田 純平; 小澤 麻由美*; 山崎 信哉*; 徳永 紘平; 福山 賢仁*; 小原 義之*; Maamoun, I.*; et al.
Chemosphere, 355, p.141837_1 - 141837_11, 2024/05
本研究では生物性マンガン酸化物を用いて人形峠坑水からのラジウム除去実験を行った。その結果、7.6mgの生物性マンガン酸化物を用いて3L坑水中から98%以上の
Raを除去することが出来た。これは固液分配係数に換算すると10
mL/gという非常に高い値となり、生物性マンガン酸化物が実際の坑水処理に有効であることを示している。
森 悠一郎*; 鍵 裕之*; 青木 勝敏*; 高野 将大*; 柿澤 翔*; 佐野 亜沙美; 舟越 賢一*
Earth and Planetary Science Letters, 634, p.118673_1 - 118673_8, 2024/05
水素による鉄の体積膨張に対するケイ素の効果を調べるため、高圧高温下でのhcp-Fe
Si
の中性子回折実験とX線回折実験を行った。中性子回折実験は重水素化hcp-FeSiに対して13.5GPa, 900K及び12.1GPa, 300Kで行い、得られたプロファイルからリートベルト解析を用いて水素占有率を決定した。hcp-Fe-SiのP-V-T状態方程式を組み合わせることにより、hcp-FeSiの水素による体積膨張が純粋なhcp鉄の体積膨張よりも10%大きいことを示した。得られた値を用いて、内核の密度欠損を再現できる水素量を見積もったところ、シリコンの影響がない場合に比べて50%減少した。hcp-FeSiで内核の密度欠損を再現した場合、内核と外核で可能な水素量xはそれぞれ0.07と0.12-0.15と計算された。
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
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.
山口 瑛子; 栗原 雄一*; 永田 光知郎*; 田中 万也; 桧垣 正吾*; 小林 徹; 谷田 肇; 小原 義之*; 横山 啓一; 矢板 毅; et al.
Journal of Colloid and Interface Science, 661, p.317 - 332, 2024/05
被引用回数：0ラジウム(Ra)は放射性元素であり、放射性廃棄物処理やウラン鉱山周辺の環境問題で重要なため、環境中Ra挙動の解明は急務である。しかし、Raは安定同位体が存在しないため分子レベルの実験が難しく、環境中で重要と考えられる粘土鉱物への吸着反応についても詳細なデータは得られていない。本研究では、広域X線吸収微細構造(EXAFS)法によりRaの分子レベルの情報を得る手法を確立し、さらに第一原理計算を利用することでRaの粘土鉱物への吸着構造を明らかにした。また、同族元素との比較を行い、粘土鉱物への吸着反応の系統的な理解に資する結果を得た。
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.
Baccou, J.*; Glantz, T.*; Ghione, A.*; Sargentini, L.*; Fillion, P.*; Damblin, G.*; Sueur, R.*; Iooss, B.*; Fang, J.*; Liu, J.*; et al.
Nuclear Engineering and Design, 421, p.113035_1 - 113035_16, 2024/05
In the Best-Estimate Plus Uncertainty (BEPU) framework, the use of best-estimate code requires to go through a Verification, Validation and Uncertainty Quantification process (VVUQ). The relevance of the experimental data in relation to the physical phenomena of interest in the VVUQ process is crucial. Adequacy analysis of selected experimental databases addresses this problem. The outcomes of the analysis can be used to select a subset of relevant experimental data, to encourage designing new experiments or to drop some experiments from a database because of their substantial lack of adequacy. The development of a specific transparent and reproducible approach to analyze the relevance of experimental data for VVUQ still remains open and is the topic of this contribution. In this paper, the concept of adequacy initially introduced in the OECD/NEA SAPIUM (Systematic APproach for model Input Uncertainty quantification Methodology) activity is formalized. It is defined through two key properties, called representativeness and completeness, that allows considering the multifactorial dimension of the adequacy problem. A new systematic approach is then proposed to analyze the adequacy of a set of experimental databases. It relies on the introduction of two sets of criteria to characterize representativeness and completeness and on the use of multi-criteria decision analysis method to perform the analysis. Finally, the approach is applied in the framework of the new OECD/NEA ATRIUM activity which includes a set of practical IUQ exercises in thermal-hydraulics to test the SAPIUM guideline in determining input uncertainties and forward propagating them on an application case. It allows evaluating the adequacy of eight experimental databases coming from the Super Moby-dick, Sozzi-Sutherland and Marviken experiments and identifying the most adequate ones.
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.
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、
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、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。
Mn清水 一行*; 西村 克彦*; 松田 健二*; 赤丸 悟士*; 布村 紀男*; 並木 孝洋*; 土屋 大樹*; Lee, S.*; 髭本 亘; 都留 智仁; et al.
Scripta Materialia, 245, p.116051_1 - 116051_6, 2024/05
質量ppmレベルの水素は金属材料の水素脆化を引き起こすが、水素の捕獲部位を実験的に解明することは極めて困難である。我々は、正ミュオンが水素の軽い同位体として作用することを利用して、物質中の水素の捕獲状態を研究した。ゼロ磁場ミュオンスピン緩和実験と密度汎関数理論(DFT)計算をAlMnに対して行った。AlMnにおける水素のDFT計算の結果、4つの水素トラップサイトが見つかり、その水素トラップエネルギーはeV/atom単位で0.168(サイト1), 0.312(サイト2), 0.364(サイト3), 0.495(サイト4)であった。推定された双極子磁場幅の温度変化(
)は、94, 193, 236Kでステップ状の変化を示した。サイト密度を考慮すると、観測されたの変化温度は、サイト1, 3, 4にミュオンがトラップされたものと解釈される。
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.
