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小泉 光生; 余語 覚文*
Isotope News, (802), p.11 - 14, 2025/12
ボリュームのある試料を非破壊で分析するには、透過力の高い放射線の利用が有効である。中性子共鳴透過分析(neutron resonance transmission analysis (NRTA))法は、パルス状の熱
熱外中性子ビームを用いて、時間分解された透過率から試料中に含まれる様々な核種の面密度(単位面積当たりの粒子数)を分析する技術である。超高強度レーザーを用いてレーザーショットにより中性子を生成するレーザー駆動中性子源(laser-driven neutron source (LDNS))は、高強度かつ短パルスの中性子を生成できることから、NRTAへの適用が期待されている。本紹介記事では、大阪大学レーザー科学研究所(ILE)のニュークリアフォトニクス(NP)グループが開発したLFEXレーザーおよびLDNSを用いて行った、NRTAによる面密度測定実証実験の概要とその結果を紹介する。
Chaerun, R. I.; 佐藤 淳也; 平木 義久; 吉田 幸彦; 佐藤 努*; 大杉 武史
Construction and Building Materials, 500, p.144270_1 - 144270_10, 2025/11
アルカリ活性化材料(AAMs)、特にメタカオリンを原料とするものは、その高密度な微細構造と化学的耐久性により、有害廃棄物の固定化に用いる持続可能なバインダーとして大きな注目を集めている。これらの非晶質アルミノケイ酸塩構造は、有害物質を効果的にカプセル化し、環境リスクを低減することができる。しかし、この非晶質ネットワークの安定性を維持することは容易ではなく、特にナトリウム(Na
))を多く含む前駆体を使用する場合、過剰なNa
が結晶化を促進し、マトリックスの完全性を損なうことが知られている。本研究では、主にカリウム(K
))で活性化されたメタカオリン系AAMsにおけるNa+濃度が構造安定性に与える影響を体系的に検討した。その目的は、非晶質構造を保持し化学的安定性を維持できるNa取り込みの閾値を明らかにすることである。透過型電子顕微鏡(TEM)、ラマン分光法、熱力学モデリングを用いて、さまざまなNa:Kモル比におけるK-AAMsの構造進化を解析した。その結果、Na:K比が高い場合には、ナノポアの形成やNaに富むゼオライト相の早期結晶化が生じ、マトリックスの安定性が低下することが明らかとなった。一方で、非晶質ネットワークを維持し、アルミノケイ酸塩骨格を保つ最適なNa:K比が特定された。これらの知見は、高耐久かつ先進的な廃棄物固定化技術に向けたK-AAMsの最適化に有用な指針を提供するものである。
和田 裕貴; 柴本 泰照; 日引 俊詞*
International Journal of Heat and Mass Transfer, 249, p.127219_1 - 127219_16, 2025/10
被引用回数:0 パーセンタイル:0.00(Thermodynamics)Two saturated boiling heat transfer correlations for downward flows in vertical circular pipes depending on wall superheat or wall heat flux as input parameters were developed based on a heat transfer experimental database. Owing to the absence of heat transfer correlations specifically developed for downward flows, existing heat transfer correlations for different flow directions were evaluated to determine their applicability to predicting the downward flow heat transfer coefficient. The results revealed that even the most accurate correlation showed a mean absolute percentage error (MAPE) of 66.5%, highlighting the need for improving predictive performance. In response, the downward flow heat transfer correlation was modeled by integrating a nucleate boiling heat transfer term and a forced convection heat transfer term. The Dong-Hibiki correlation, a two-component, two-phase heat transfer correlation for downward flows, was adopted for the forced convection heat transfer term. The Forster-Zuber correlation, developed as a wall superheat function, and the Cooper correlation, developed as a wall heat flux function, were used for the nucleate boiling term to develop the heat transfer correlations where either wall superheat or wall heat flux is known. Notably, the Dong-Hibiki correlation has been validated over a wide range of experimental conditions. A correction factor was applied to the nucleate boiling term to address errors caused by applying Foster-Zuber and Cooper correlations to downward flows. The two developed correlations achieved an MAPE value of approximately 20%, representing an improvement of roughly 40% over existing correlations of heat transfer coefficients.
山口 雄司; 近藤 恭弘; 明午 伸一郎; 篠崎 信一; 高柳 智弘; 藤森 寛*; 河村 成肇*
Journal of Physics; Conference Series, 3094(1), p.012023_1 - 012023_5, 2025/09
J-PARCでは、3GeV陽子ビーム輸送施設によって3GeVシンクロトロンから物質・生命科学実験施設(MLF)へ大強度陽子ビームを輸送している。陽子ビーム輸送施設のビームライン最下流部には、ミュオンビーム輸送用の偏向電磁石とソレノイドがあるため、これらの磁場による3GeV陽子ビームへの影響を補正する必要がある。シミュレーションにより偏向電磁石による軌道のずれとソレノイドによるプロファイルの回転に伴う垂直方向ビームサイズの増大を模擬し、それぞれの影響を補正する方法を検討した結果、追加の偏向電磁石とソレノイドを用いることで補正でき、安定なビーム輸送が可能であることがわかった。
佐藤 理花; 近藤 俊樹; 梅田 良太; 菊地 晋; 山野 秀将
Progress in Nuclear Science and Technology (Internet), 8, p.137 - 142, 2025/09
ナトリウム-溶融塩熱交換器を有する蓄熱式高速炉では、ナトリウム(Na)と硝酸系溶融塩との熱交換器伝熱管破損に至るような仮想的な事故条件下でNaと硝酸系溶融塩との化学反応が発生する可能性がある。そのため、Naと硝酸系溶融塩の反応挙動は、当該システムの安全評価上、重要現象の一つとなっている。本研究では、NaNO
-KNO
の混合物であるソーラーソルトとNaとの反応試験を実施し、得られた試験結果について検討を行った。その結果、ソーラーソルトの融解が開始した後にNaとの反応が起こることが分かった。試験で得られた反応温度から、速度論的パラメータおよび反応速度を求め、Na-水反応と比較した。その結果、Na-溶融塩熱交換器を有する蓄熱式高速炉の伝熱管破損時の事象進展で勘案すべき時間スケール内にソーラーソルト反応が生じ得ることが分かった。
戸田 賀奈子*; 元川 竜平; 斉藤 拓巳*
Journal of Physical Chemistry C, 11 Pages, 2025/08
被引用回数:0 パーセンタイル:0.00The development of the nano-scale pore size distribution of metakaolin-based geopolymers (MKGPs) was evaluated by the application of the small-angle neutron scattering (SANS), followed by the polydisperse spherical (PDSP) model application, where the modelled outputs were then deconvoluted by bimodal log-normal distribution fitting. Small pores, with a log-normal distribution modal value of 2.5 nm, immediately formed after mixing, with a decrement in the pore volume as a function of time. Larger pore size distribution with log-normal distribution modal values larger than 4nm, required an induction period, indicating the larger pore size distribution evolution corresponds to the pores as aluminosilicate cluster gel interstices. The nano-scale pore size distribution development varied by the curing temperature and the type of activators, which were evaluated in this study. The initial pore evolution of the MKGPs may be the critical step in determining the nano-sized porosity of the MKGPs, which characterizes the diffusive property of the material, such as the De of HDO.
-butadiene) reinforced by carbon blackWatanabe, Yuki*; 熊川 大幹*; Karitani, Shu*; 井上 正志*; 岩蕗 仁*; 中西 洋平*; 柴田 基樹*; 元川 竜平; 杉田 剛; 上田 祐生; et al.
Macromolecules, 58(16), p.8641 - 8648, 2025/08
被引用回数:0 パーセンタイル:0.00We investigated how the particle size of carbon black (CB) affects the reinforcement of CB to vulcanized poly(styrene-co-butadiene) (SBR) in the glassy region. When the average diameter of CB d is larger than 100 nm, the enhancement of modulus can be expressed by the Eshelby/Mori-Tanaka model, which agrees with the results obtained for an SBR/silica system. On the other hand, at d
100nm, the volume fraction dependence of the enhancement becomes stronger than the theory's prediction. The scattering studies on the SBR/CB systems revealed that the aggregates of CB at d
100nm consist of densely packed CB, while the aggregates of CB at d
100nm exhibit branch structures. At d
100nm, the voids or the occluded region in the packed CB increase the volume fraction, resulting in a stronger volume fraction dependence of the enhancement.
武井 早憲
Journal of Nuclear Science and Technology, 45 Pages, 2025/06
被引用回数:0 パーセンタイル:0.00日本原子力研究開発機構では、マイナーアクチニドを効率的に核変換する加速器駆動核変換システム(ADS)の研究開発を行っている。このシステムは、未臨界炉と大強度超伝導陽子線形加速器(ADS用陽子加速器)の組み合わせである。ADS用陽子加速器の開発を困難にしている要因の一つは、熱サイクル疲労を誘因するビームトリップ事象であり、この事象によって未臨界炉の機器が損傷するからである。ADS用陽子加速器は大強度陽子加速器の一つであるJ-PARCリニアックと比べて電流比で32倍の差がある。従って、開発段階に応じてADS用陽子加速器のビームトリップ頻度と許容ビームトリップ頻度を比較することが必要になる。今回、J-PARCリニアックの運転データに基づく信頼度関数を使ったモンテカルロ法のプログラムを作成し、ADS用陽子加速器のビームトリップ頻度を推測した。モンテカルロ法のプログラムにより、従来の解析手法では得られなかったビームトリップ事象の時間分布が得られた。その結果、許容ビームトリップ頻度を満足するには、ビームトリップ時間が5分以上のビームトリップ頻度を現状の27%に低減しなければならないことがわかった。
上田 祐生; Micheau, C.; 元川 竜平
ファインケミカル, 54(5), p.53 - 60, 2025/05
持続可能な社会を実現するためには金属資源のリサイクルが重要である。高濃度の金属イオンを取り扱う抽出操作では、プロセスの安全な運転を阻害する油相の相分離(第三相の生成)が長年の課題であった。本稿では、フルオラス化合物の強力な疎水性を利用した、第三相を生成させない新たな抽出系開発におけるこれまでの成果をまとめた。
友田 陽*; Harjo, S.; 徐 平光; 諸岡 聡; Gong, W.; Wang, Y.*
Metals, 15(6), p.610_1 - 610_19, 2025/05
被引用回数:0 パーセンタイル:0.00(Materials Science, Multidisciplinary)Lattice parameters of product and matrix phases in steels have been measured using in situ X-ray and neutron diffraction during forward and reverse transformations. These parameters are influenced by temperature, transformation-induced internal stresses, alloying element partitioning, crystal defects, and magnetic strains. Disentangling these contributions is essential for understanding lattice behavior. This review explores internal strain (stress) associated with ferrite, pearlite, bainite, martensite, and reverse austenite transformations, emphasizing the distinction between diffusional and displacive mechanisms. It also examines how plastic deformation of austenite affects subsequent bainite or martensite formation. The roles of dislocations and vacancies are identified as critical areas for further research.
福田 航大; 小原 徹*; 須山 賢也
Nuclear Technology, 211(5), p.963 - 973, 2025/05
被引用回数:1 パーセンタイル:35.03(Nuclear Science & Technology)An application of the boiling water reactor (BWR) to an offshore floating nuclear power plant (OFNP) is discussed in Japan. The BWR-type OFNP has some challenges for practical use, although it has high economic efficiency because of downsizing and simplification. One challenge is understanding reactor kinetics under conditions specific to the marine environment. This study quantitatively clarifies the total and spatial changes in power when the BWR is inclined during regular operation. Therefore, the TRAC/RELAP Advanced Computational Engine (TRACE) and Purdue Advanced Reactor Core Simulator (PARCS) codes were used to perform a three-dimensional neutronics-thermal-hydraulics-coupled transient analysis. The calculation model is based on Peach Bottom II. This study clarifies the changing trend in total and local BWR power by inclination with simplified modeling and conditions. Reasons for such changes are discussed based on changes in several thermal-hydraulic parameters. The difference in BWR power against the inclinations is small. Thus, it was implied that the BWR-type OFNP is expected to have a stable power supply capability during natural disasters. Finally, requires further studies to support the obtained conclusions are discussed.
和田 裕貴; 柴本 泰照; 日引 俊*
International Journal of Heat and Mass Transfer, 239, p.126598_1 - 126598_18, 2025/04
被引用回数:4 パーセンタイル:46.60(Thermodynamics)This study reviewed the saturated boiling heat transfer research in downward flows. A database of downward flow heat transfer experiments was created using experimental studies. Saturated boiling heat transfer correlations in internal flows were collected, and no downward flow-specific heat transfer correlations were identified. The applicability of heat transfer correlations to downward flow heat transfer experiments was evaluated, and no correlation could predict the heat transfer coefficients accurately for all experimental databases. However, correlations that could predict heat transfer coefficients reasonably well were determined for each channel size. Cooper's correlation [Int. Chem. Eng. Symp. Ser. 86 (1984) 785-792] had a mean absolute percentage error (MAPE) of 11.7% for mini-channels and Kim and Mudawar's correlation [Int. J. Heat Mass Transf. 64 (2013) 1239-1256] had an MAPE of 66.5% for macro-channels. Furthermore, because the advection direction between the liquid-phase and the generated bubbles differed depending on the liquid-phase velocity in downward flows, we evaluated the prediction performance of the heat transfer coefficient for the liquid-phase velocity. For some experimental data, the prediction performance of the existing correlation for downward flow heat transfer worsened as the advection velocity of the bubbles decreased. This result is one of the issues to be addressed in the future development of heat transfer correlations.
林崎 康平; 廣岡 瞬; 山田 忠久*; 砂押 剛雄*; 村上 龍敏; 齋藤 浩介
Ceramics (Internet), 8(1), p.24_1 - 24_12, 2025/03
Zirconolite is a wasteform that can immobilize Pu. Herein, zirconolites comprising Ce as a Pu simulant and Al as a charge compensator of Ce/Pu were synthesized by sintering raw CaO, ZrO
, TiO
, CeO
, and Al
O
powder mixtures at 1400
C in static air. The reduction behavior and phase transformation of zirconolites during their heat treatment in an Ar-H
gas flow were investigated. All zirconolite compositions first underwent reduction at
1050
C by forming a small domain of perovskite phase. Ce-Al co-doped zirconolite showed a smaller fraction of phase transformation in perovskite than Ce-doped zirconolite, indicating the advantage of using a charge compensator to prevent perovskite formation.
Guembou Shouop, C. J.; 土屋 晴文
Nuclear Instruments and Methods in Physics Research A, 1072, p.170189_1 - 170189_14, 2025/03
被引用回数:2 パーセンタイル:59.21(Instruments & Instrumentation)The development of a compact mobile neutron resonance transmission analysis (NRTA) instrument is in progress for measuring nuclear materials in the field of nuclear nonproliferation and nuclear security. The present paper focuses on research/developments on designing the source, moderators and shielding for the table-top NRTA system utilising a
Cf spontaneous neutron. To this end, three source configurations were assessed using Monte Carlo (MC) simulations-based Particle and Heavy Ion Transport code System (PHITS) by evaluating each configuration's neutron/gamma fluxes. Experimental validation of the MC simulation was conducted using an EJ270 plastic scintillation detector, a
Bq
Cf source, and a thin In sample. The Monte Carlo simulations and experimental results confirmed that an optimal configuration for the table-top NRTA system involves sandwiching the
Cf source between the polyethylene (PE) moderator (PE closer to the detector) and the W reflector. Furthermore, the MC simulations showed that resonance dips from NatU and Pu (energy lines of 1.06 and 2.60 eV of
Pu and 0.30 eV of
Pu) can be observed in the Time-of-Flight spectra obtained using the table-top NRTA system with an appropriate collimator for a small pellet sample. The preliminary experimental results with a 2 mm thick In sample displayed the 1.46 eV resonance dip of
In, showing that the table-top NRTA system using a
Cf neutron source can measure TOF spectra and observe dips caused by low energy resonances in a sample. These findings suggest the system is well-suited for measuring small pellet samples of Pu and U.
北條 智彦*; 小山 元道*; 熊井 麦弥*; Zhou, Y.*; 柴山 由樹; 城 鮎美*; 菖蒲 敬久; 齋藤 寛之*; 味戸 沙耶*; 秋山 英二*
ISIJ International, 65(2), p.284 - 296, 2025/02
被引用回数:0 パーセンタイル:0.00(Metallurgy & Metallurgical Engineering)Stress and plastic strain distributions and those partitioning behaviors of ferrite and retained austenite were investigated in the medium manganese (Mn) and the transformation-induced plasticity-aided bainitic ferrite (TBF) steels, and the martensitic transformation behaviors of retained austenite during Luders elongation and work hardening were analyzed using synchrotron X-ray diffraction at SPring-8. The stress and plastic strain of retained austenite and volume fraction of retained austenite were remarkably changed during Luders deformation in the medium Mn steel, implying that the medium Mn steel possessed inhomogeneous deformation at the parallel part of the tensile specimen. On the other hand, the distributions of the stress, plastic strain and volume fraction of retained austenite were homogeneous and the homogeneous deformation occurred at the parallel part of the tensile specimen at the plastic deformation regime with work hardening in the medium Mn and TBF steels. The martensitic transformation of retained austenite at uders deformation in the medium Mn steel was possessed owing to the application of high stress and preferential deformation at retained austenite, resulting in a significant increase in the plastic deformation and reduction of stress in the retained austenite. The martensitic transformation of retained austenite at the plastic deformation regime with work hardening was induced by the high dislocation density and newly applied plastic deformation in retained austenite in the medium Mn steel whereas the TBF steel possessed gradual transformation of retained austenite which is applied high tensile stress and moderate plastic deformation.
大西 貴士; 小山 真一*; 横山 佳祐; 森下 一喜; 渡部 雅; 前田 茂貴; 矢野 康英; 大木 繁夫
Nuclear Engineering and Design, 432, p.113755_1 - 113755_17, 2025/02
被引用回数:0 パーセンタイル:0.00(Nuclear Science & Technology)The burning of minor actinide (MA) elements, such as neptunium (Np) and americium (Am), in fast reactors (FRs) has been proposed to reduce the volume of high-level radioactive waste. Evaluation of the transmutation behavior of Am for a wide spectral range from thermal to fast neutrons requires experimental validation based on the irradiation of Am targets with well-known isotopic compositions. Four samples each of two types of Am targets, Am-241 oxide and Am-243 oxide, were prepared and irradiated in the experimental fast reactor Joyo under fast neutron flux. Additionally, a ninth sample consisting of Am-241 oxide contained in a MgO pellet was prepared and irradiated in the JMTR under thermal neutron flux. All irradiated samples were analyzed by a radiochemical method. Indexes of the transmutation behavior such as the transmutation ratio, the ratio between burnup and accumulation of an actinide could be evaluated based on the analytical results.
Yoshida, M.*; McDermott, R. M.*; Angioni, C.*; Camenen, Y.*; Citrin, J.*; Jakubowski, M.*; Hughes, J. W.*; 井戸村 泰宏; Mantica, P.*; Mariani, A.*; et al.
Nuclear Fusion, 65(3), p.033001_1 - 033001_132, 2025/02
被引用回数:7 パーセンタイル:95.54(Physics, Fluids & Plasmas)ITER Physics Basis出版以降のITPA輸送・閉じ込め(TC)グループにおけるプラズマ輸送と閉じ込めの物理理解と理論モデル開発の進展を、ITERと燃焼プラズマの予測・制御への貢献に焦点を当ててまとめた。本論文は、過去15年間のITPA TC共同実験/共同活動によって主に導かれた進歩について、一般的かつ合理的な概観を提供するものである。本論文は、ITPA TCグループの科学的な戦略とスコープ、主要な進歩の全体像から始まり、粒子輸送、不純物輸送、イオン・電子乱流熱輸送、運動量輸送、3次元磁場が輸送に与える影響、閉じ込めモード遷移、大域的閉じ込め、簡約化輸送モデルといった各研究分野の進歩を示す。
Yang, X.*; Che, G.*; Wang, Y.*; Zhang, P.*; Tang, X.*; Lang, P.*; Gao, D.*; Wang, X.*; Wang, Y.*; 服部 高典; et al.
Nano Letters, 25(3), p.1028 - 1035, 2025/01
被引用回数:2 パーセンタイル:82.57(Chemistry, Multidisciplinary)飽和sp
-カーボンナノスレッド(CNTh)は、その高いヤング率と熱伝導率が予測され、大きな関心を集めている。中心環へのヘテロ原子の導入がCNThの形成に影響を与え、化学的に均質な生成物が得られることが示されているが、ペンダント基が重合プロセスに与える影響については、まだ未解明である。本研究では、フェノールの圧力誘起重合を調べ、0.5GPaと4GPa以下で起こる2つの相転移を明らかにした。20GPa以上では、フェノールは水酸基とカルボニル基を持つ重合度4のCNTに重合する。ヒドロキシル基の水素移動は、重合度6のナノスレッドの形成を妨げることがわかった。この発見は、さらなるカラム内重合を阻止する水酸基の重要な役割を浮き彫りにし、今後のメカニズム研究やナノ材料合成に貴重な示唆を与えるものである。
Metcalfe, R.*; Benbow, S. J.*; 川間 大介*; 舘 幸男
Science of the Total Environment, 958, p.177690_1 - 177690_17, 2025/01
花崗岩が隆起している条件を対象とした地層処分の安全評価においては、隆起による地質条件の変化とそれに伴う放射性核種の移行・遅延特性への影響を考慮する必要がある。このような地質環境の長期変遷を考慮した安全評価では、十分に現実的な数値モデルと適切なパラメータを適用する必要がある。しかしながら、隆起過程には、岩石特性や核種移行特性の変化などを含む複雑な連成現象が含まれるため、モデルの開発には困難を伴う。ここでは、いくつかの代表的な放射性核種を対象とした連成モデル解析を通じて、現実的で保守的なプロセスの概念化とモデルパラメータの設定を検討するための方法論を提示する。
Johansen, M. P.*; Gwynn, J. P.*; Carpenter, J. G.*; Charmasson, S.*; McGinnity, P.*; 森 愛理; Orr, B.*; Simon-Cornu, M.*; Osvath, I.*
Critical Reviews in Environmental Science and Technology, 55(6), p.422 - 445, 2025/00
被引用回数:3 パーセンタイル:23.85(Environmental Sciences)Seafood is an important source for meeting future global nutrient demands. However, it also contributes disproportionately to the radiological ingestion dose of more than five billion world consumers - up to
70%-80% of the total-foods dose in some countries. Although numerous studies report seafood doses in specific populations, there is still no comprehensive evaluation answering basic questions such as "what is the ingestion dose to the average global seafood consumer?" Analysis of 238 worldwide seafood dose estimates suggests that typical adult consumers receive from 0.13 to 0.21 mSv, with a likely best estimate of 0.15 mSv per annual seafood intake. Those consuming large amounts of seafood, particularly bivalves, may experience ingestion doses exceeding 1 mSv per annual intake, surpassing other routine background dose sources. The published studies suggest that doses of 3 mSv or greater are surpassed in about 150 million adult seafood consumers worldwide. Almost all this dose comes from the natural radionuclides that are prevalent in marine systems - especially
Po. While trace levels of anthropogenic radionuclides are ubiquitous in seafoods (e.g.,
Cs and
Pu), the added dose from these is typically orders of magnitude lower. Even following the large-scale releases from the Fukushima accident, with food safety controls in place, the additional dose to consumers in Japan was small relative to routine dose from natural background radionuclides. However, the worldwide seafood dose estimates span seven orders of magnitude, indicating a need for an assessment that integrates global seafood radionuclide data as well as incorporating changes in seafood consumption and production patterns.