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論文

Investigating eutectic behavior and material relocation in B$$_{4}$$C-stainless steel composites using the improved MPS method

Ahmed, Z.*; Wu, S.*; Sharma, A.*; Kumar, R.*; 山野 秀将; Pellegrini, M.*; 横山 諒*; 岡本 孝司*

International Journal of Heat and Mass Transfer, 250, p.127343_1 - 127343_17, 2025/11

 被引用回数:2 パーセンタイル:69.40(Thermodynamics)

The study aims to measure boron concentration through the unidirectional diffusion of boron within the stainless steel (SS) layers while evaluating the updated model ability to replicate melt relocation behavior and geometry. In the current MPS simulations, one scenario employed dummy walls as heat sources, while another scenario used SS surface particles as heat sources to avoid interference with the melt flow as it reached the bottom of the specimen.

論文

Computation of the heat capacity of water from first principles

志賀 基之; Elsner, J.*; Behler, J.*; Thomsen, B.

Journal of Chemical Physics, 163(13), p.134119_1 - 134119_13, 2025/10

水は高い熱容量などの特異な性質を持ち、生命や気候に重要な役割を果たしている。その熱容量の微視的起源を第一原理から理解するには、核の量子効果を考慮した高精度な経路積分分子動力学(PIMD)シミュレーションが必要であるが、計算コストが非常に高い。本研究では、密度汎関数理論(DFT)に基づいた高次元ニューラルネットワークポテンシャル(HDNNP)を用いることで、この課題を克服している。さらに、高効率なPIMDアルゴリズムを導入し、熱容量の収束データを得ることに成功した。特にrevPBE0-D3汎関数を用いた結果は実験と良く一致し、本手法が水の熱力学的性質の定量的理解に有効であることを示している。

論文

Unveiling the local effects of PTL passivation in PEM Electrolyzers through gas and current mapping using operando neutron radiography and polarized neutron imaging

Karimi, V.*; Qvistgaard, C. H.*; Schmidt, S.*; Wolfertz, A.*; Parker, J. D.*; 甲斐 哲也; 林田 洋寿*; 篠原 武尚; Angelis, S. D.*; Tengattini, A.*; et al.

ACS Applied Materials & Interfaces, 17(36), p.50742 - 50752, 2025/08

 被引用回数:0 パーセンタイル:0.00

Anodic Ti-based porous transport layers (PTLs) are paramount for advancing high-efficiency proton exchange membrane water electrolyzers (PEMWEs). One of the major challenges with the development of PEMWE is the PTL/catalyst layer interface passivation, which is commonly alleviated by coating precious metals such as Pt. Herein, we report, for the first time, the usage of polarized neutron imaging (PNI) on a half-half PTL approach to investigate current distribution inside the PTL layer under the influence of Ti passivation under PEMWE operando condition. First, the electrochemical study of PEMWE reveals an obvious advantage of Pt coating in preventing Ti passivation by showing 822 mV less overpotential at 1 A cm$$^{-2}$$ (1.771 V) for the superior sample (Pt-coated PTL) compared to the PEMWE with pristine Ti PTL (2.539 V). Second, it is confirmed that using ex situ electronic and structural characterizations, Ti passivation cannot be recognized, suggesting a temporary passivation process in an operating PEMWE. Employing PNI for operando mapping of the current distribution inside the PEMWE shows that most of the electrical current favors the Pt-coated PTL, perfectly aligned with the results obtained from the high-resolution operando neutron radiography in which around 60% of the produced oxygen was found in the Pt-coated PTL.

論文

Deciphering the third phase structure in uranium extraction with aliphatic amines using combined small-angle X-ray and neutron scattering

Guerinoni, E.*; Zemb, T.*; 元川 竜平; 上田 祐生; 青柳 登; Pellet-Rostaing, S.*; Dourdain, S.*

Journal of Physical Chemistry B, 129(32), p.8210 - 8217, 2025/08

 被引用回数:0 パーセンタイル:0.00

Liquid-liquid extraction of uranium involves an acidic aqueous phase in contact with an oil phase containing aliphatic amines and a linear alkane. Excess electrolyte in the oil phase leads to a third phase, hindering metal ion extraction and stripping. We determine the largest admissible extractant concentration (LOC) before macroscopic phase separation. Using small-angle X-ray scattering (SAXS) and small-angle neutron scattering (SANS), we analyze the microstructure of the phases. In all aliphatic diluents, the third phase consists of weak water-in-oil (w/o) aggregates with interdigitated hydrocarbon chains. Even after centrifugation, SANS detects residual deuterated solvent molecules. A fraction of these w/o aggregates contains uranium(VI) cations (U-loaded aggregates), which exhibit stronger attractive interactions than unloaded aggregates. This leads to the segregation of U-loaded aggregates into large clusters, detected as a Porod-type decay in SAXSbut absent in SANS at a low q-values.

論文

Recommendations on fuel properties for fuel performance codes

Chauvin, N.*; Martin, P.*; 尾形 孝成*; Calabrese, R.*; Janney, D.*; 廣岡 瞬; 加藤 正人; Staicu, D.*; McClellan, K.*; White, J.*; et al.

NEA/NSC/R(2024)1 (Internet), 289 Pages, 2025/07

OECD/NEAのWorking Party on Scientific Issues of Advanced Fuel Cycles(WPFD)/Expert Group on Innovative Fuel Elementsでは、各国の核燃料研究の専門家による協力のもとで、酸化物及び金属燃料を対象とした推奨燃料物性値を取りまとめ、燃料照射挙動解析コードのベンチマークに反映する活動を行ってきた。本報告は、公開文献をベースに推奨燃料物性値を取りまとめたものであり、格子定数、融点、熱膨張、熱伝導率、比熱、弾性率、酸素ポテンシャル及び相変化について、物性値、評価式及びそれらの適用範囲を示す。

論文

Methods for regulating depth of corrosion fissures in simulated fastener holes of 7050-T7451 aluminum alloy

青山 高士; Choudhary, S.*; Pandaleon, A.*; Burns, J. T.*; Kokaly, M.*; Restis, J.*; Ross, J.*; Kelly, R. G.*

Corrosion, 81(6), p.609 - 621, 2025/06

 被引用回数:1 パーセンタイル:67.80(Materials Science, Multidisciplinary)

This study presents a new test method for inducing controlled corrosion damage within simulated fastener holes of aluminum alloys, aimed at pretreating fatigue test specimens. The method involves insulating the outer surface while exposing the fastener hole surface to electrolytes containing 0.66 M NaCl + 0.1 M AlCl $$_{3}$$ with varying concentrations of K $$_{2}$$S $$_{2}$$O $$_{8}$$. The evolution of corrosion damage within the fastener hole was examined as a function of exposure duration, electrolyte composition, and volume, as well as the effect of galvanic coupling with a SS316 cathode. Results indicate that fissure depth increases with an increase in K $$_{2}$$S $$_{2}$$O $$_{8}$$ concentration but does not progress further after 24-48 hours of exposure in the chemical, or freely-corroding, exposure test. In contrast, galvanic coupling with a SS316 plate significantly accelerates corrosion, leading to much deeper fissures in a shorter time. The importance of electrolyte replenishment has been explored using electrochemical measurements, revealing the impact of evolving electrolyte chemistry. Beyond its application in fatigue specimen pretreatment, this method provides a simple yet effective approach for studying localized corrosion and evaluating mitigation strategies for fastener holes in aerospace structures.

論文

Modification of single-hole-like states by configuration mixing in $$^{99-131}$$In

Patel, D.*; Srivastava, P. C.*; 清水 則孝*; 宇都野 穣

Physical Review C, 111(6), p.064303_1 - 064303_13, 2025/06

 被引用回数:0 パーセンタイル:0.00

In同位体は陽子数50の魔法数から1つだけ少ない陽子数をもつため、陽子の一粒子エネルギーを強く反映しているとされている。これらの同位体に対し、大規模殻模型計算を行った結果、これまでは重要でないと考えられていた$$p_{3/2}$$軌道や$$f_{5/2}$$軌道の配位混合が第一励起準位を正しく得るのに大きな役割を果たすことがわかった。最近測定された磁気モーメント、四重極モーメントや、分光学的因子もよく再現されるとともに、この描像がよく成り立つことがわかった。

論文

Impact of microdosimetric modeling on computation of relative biological effectiveness for carbon ion radiotherapy

Hartzell, S.*; Furutani, K. M.*; Parisi, A.*; 佐藤 達彦; 加瀬 優紀*; Deglow, C.*; Friedrich, T.*; Beltran, C. J.*

Radiation (Internet), 5(2), p.21_1 - 21_24, 2025/06

Microdosimetry is essential in particle therapy for understanding the biological effects of treatments by quantifying energy depositions within microscopic volumes. The calculation of the microdosimetric distributions can be carried out with physical models such as the Kiefer-Chatterjee (KC) track structure function and the Sato analytical microdosimetric function (AMF). Comprehensive comparisons across these physical models are lacking. The AMF is calculated for spherical domains, while the KC is traditionally calculated for a cylindrical domain. This study introduces a novel version of the KC function for spherical domains, allowing a direct comparison with AMF. The influence of each function on the calculation of the relative biological effectiveness (RBE) in carbon ion radiotherapy (CIRT) was evaluated.

論文

Incommensurate antiferromagnetism in UTe$$_2$$ under pressure

Knafo, W.*; Thebault, T.*; Raymond, S.*; Manuel, P.*; Khalyavin, D. D.*; Orlandi, F.*; Ressouche, E.*; Beauvois, K.*; Lapertot, G.*; 金子 耕士; et al.

Physical Review X, 15(2), p.021075_1 - 021075_16, 2025/05

 被引用回数:0 パーセンタイル:0.00(Physics, Multidisciplinary)

The discovery of multiple superconducting phases in UTe$$_2$$ boosted research on correlated-electron physics. This heavy-fermion paramagnet was rapidly identified as a reference compound to study the interplay between magnetism and unconventional superconductivity with multiple degrees of freedom. The proximity to a ferromagnetic quantum phase transition was initially proposed as a driving force to triplet-pairing superconductivity. However, we find here that long-range incommensurate antiferromagnetic order is established under pressure. The propagation vector k$$_{rm m}$$ = (0.07, 0.33, 1) of the antiferromagnetic phase is close to a wavevector where antiferromagnetic fluctuations have previously been observed at ambient pressure. These elements support that UTe$$_2$$ is a nearly-antiferromagnet at ambient pressure. Our work appeals for theories modelling the evolution of the magnetic interactions and electronic properties, driving a correlated paramagnetic regime at ambient pressure to a long-range antiferromagnetic order under pressure. A deeper understanding of itinerant-f-electrons magnetism in UTe$$_2$$ will be a key for describing its unconventional superconducting phases.

論文

Extending TOPAS with an analytical microdosimetric function; Application and benchmarking with nBio track structure simulations

Hartzell, S.*; Parisi, A.*; 佐藤 達彦; Beltran, C. J.*; Furutani, K. M.*

Physics in Medicine & Biology, 70(10), p.105010_1 - 105010_19, 2025/05

 被引用回数:0 パーセンタイル:0.00(Engineering, Biomedical)

In this study, we presented the implementation of the Analytical Microdosimetric Function (AMF) within the TOPAS Monte Carlo platform as an efficient and accurate surrogate for track structure simulations. The AMF extension demonstrated strong agreement with TOPAS nBio track structure simulations for ions relevant to particle therapy and space applications, while offering significant computational advantages.

論文

Densities, surface tensions, and viscosities of molten high-silicon electrical steels with different silicon contents

Neubert, L.*; Bell$'e$, M. R.*; 山本 泰生*; 西 剛史*; 山野 秀将; Ahrenhold, F.*; Volkova, O.*

Steel Research International, 96(5), p.202400237_1 - 202400237_8, 2025/05

 被引用回数:2 パーセンタイル:40.92(Metallurgy & Metallurgical Engineering)

Density, surface tension, and viscosity of various liquid electrical steels are measured at different temperatures, varying in their silicon content between 3 and 6mass%.

論文

Density, surface tension, and viscosity of molten Ni-based superalloys using the maximum bubble pressure and oscillating crucible methods

西 剛史*; 松本 早織*; 山野 秀将; 林 喜一郎*; 遠藤 理恵*; Bell$'e$, M. R.*; Neubert, L.*; Volkova, O.*

Steel Research International, 96(5), p.2300766_1 - 2300766_6, 2025/05

 被引用回数:5 パーセンタイル:72.95(Metallurgy & Metallurgical Engineering)

ニッケル基超合金について、密度は最大気泡圧法、粘度はるつぼ振動法、表面張力は最大気泡圧法により、測定データを得た。

論文

Incorporation of boron into metakaolin-based geopolymers for radionuclide immobilisation and neutron capture potential

Niu, X.*; Elakneswaran, Y.*; Li, A.*; Seralathan, S.*; 菊池 亮佑*; 平木 義久; 佐藤 淳也; 大杉 武史; Walkley, B.*

Cement and Concrete Research, 190, p.107814_1 - 107814_17, 2025/04

 被引用回数:2 パーセンタイル:82.67(Construction & Building Technology)

Metakaolin-based geopolymers have attracted significant interest in decontaminating radioactive debris from the Fukushima nuclear accident. This study explored the incorporation of boron (B) into geopolymers using boric acid as the source, with the goal of developing B-enriched geopolymers for enhanced radionuclide immobilisation and neutron capture potential.

論文

Competition between mass-symmetric and asymmetric fission modes in $$^{258}$$Md produced in the $$^{4}$$He + $$^{254}$$Es reaction

西尾 勝久; 廣瀬 健太郎; 牧井 宏之; Orlandi, R.; Kean, K. R.*; 塚田 和明; 豊嶋 厚史*; 浅井 雅人; 佐藤 哲也; Chiera, N. M.*; et al.

Physical Review C, 111(4), p.044609_1 - 044609_12, 2025/04

 被引用回数:0 パーセンタイル:0.00(Physics, Nuclear)

In spontaneous fission (SF) it is found that the mass-asymmetric fission of well-known actinides suddenly changes to the symmetric fission when nucleus has a mass number $$A_{c}$$ larger than 257. We have measured for the first time fission-fragment mass and total-kinetic-energy (TKE) distributions of the excited compound nucleus $$^{258}$$Md, populated in the reaction $$^{4}$$He+$$^{254}$$Es, using the rare isotope $$^{254}$$Es with a short half-life, $$T_{1/2}$$=276 days. The fission of $$^{258}$$Md can be interpreted as involving 3 fission modes: an mass-asymmetric mode and two modes of mass-asymmetric fissions, the latter two are manifested by different TKE values. Predominantly symmetric fission was obtained at the excitation energy of 15.0 MeV. By increasing the energy to 18.0 MeV, the asymmetric fission mode dominates. Both such a strong change of fission modes within a small increase of excitation energy and the enhancement of asymmetric split are new phenomena in fission.

論文

Evaluation of uranium-233 neutron capture cross section in keV region

大塚 直彦*; 多田 健一; Cabellos, O.*; 岩本 修

Annals of Nuclear Energy, 212, p.110977_1 - 110977_9, 2025/03

 被引用回数:2 パーセンタイル:62.28(Nuclear Science & Technology)

ロスアラモス国立研究所のLANCEにて測定された新しい$$alpha$$測定値を考慮して、3keVから1MeVの範囲のU-233の中性子捕獲断面積を評価した。得られた捕獲断面積は、JENDL-5の捕獲断面積よりも系統的に小さく、20keV付近では50%近く減少することとなった。新しく評価された断面積の妥当性を確認するため、ISCBEPハンドブックから選択された166の臨界実験を対象に、U-233の中性子捕獲断面積について、JENDL-5のデータを新たに評価した値に置き換えた上で、モンテカルロ中性子輸送計算を実行した。その結果、新しく評価された捕獲断面積の採用により、JENDL-5のU-233を用いた場合に比べてカイ2乗値がわずかに改善することが分かった。

論文

Built-in physics models and proton-induced nuclear data validation using MCNP, PHITS, and FLUKA; Impact on the shielding design for proton accelerator facilities

$c{C}$elik, Y.*; Stankovskiy, A.*; 岩元 大樹; 岩元 洋介; Van den Eynde, G.*

Annals of Nuclear Energy, 212, p.111048_1 - 111048_12, 2025/03

 被引用回数:1 パーセンタイル:37.73(Nuclear Science & Technology)

The MCNP, PHITS, and FLUKA are general-purpose Monte Carlo radiation transport codes that are widely used for many real-world shielding problems at accelerator facilities around the world. For high beam energy and high beam current accelerator applications, neutron emission through the vacuum pipe along the reverse direction of incident proton beam is an important factor for a shielding design in order to correctly assess the dose rates for workers and the structural materials of the accelerator and handle with the waste activated by the backscattered neutron fluxes. In this work, neutron-production cross sections and thick target yield predictions from MC codes relying on physics models and nuclear data libraries are benchmarked against the experimental data, in order to assess their accuracy in predicting neutron emission and furthermore to assess the corresponding impact on shielding design. The results of this study demonstrate that the nuclear data libraries and physics models, which are not expected to give good results at lower energies ($$< 150$$ MeV) but are used anyhow when there is no nuclear data available or above the energy range where the data tables end in the so-called "mix-and-match" strategy, need further improvements. Among the investigated proton induced nuclear data libraries, JENDL-4.0/HE produces the most satisfactory agreement to experimental data for all target materials, but may still benefit from refinement. Concerning the physics models of the codes, FLUKA V4-4.0 has the best performance in terms of reproducibility of the experimental values. It is also shown that all discrepancies between the calculations and the experiments for the energy range $$< 10$$ MeV are up to factor of two. This might be considered as an acceptable figure as it is equivalent to a normal safety margin ($$times 2$$) considered in shielding calculations of accelerator facilities around the world.

論文

Radiation heating effects on B$$_{4}$$C-SS eutectic melting and its relocation behaviour

Ahmed, Z.*; Sharma, A. K.*; Pellegrini, M.*; 山野 秀将; 岡本 孝司*

Arabian Journal for Science and Engineering, 50(5), p.3361 - 3371, 2025/03

 被引用回数:2 パーセンタイル:62.28(Multidisciplinary Sciences)

This study pioneers the use of radiative heating for high-resolution visualisation and quantification of the eutectic melt composition, providing a novel approach to observing the melting and candling phenomena. Key findings include two distinct failure processes: SS cladding detachment forming molten droplets and fragmentation of B$$_{4}$$ pellets, with sintering observed in B$$_{4}$$ powder.

論文

Magnetite stoichiometry (Fe(II)/Fe(III)) controls on trivalent chromium surface speciation

Scaria, J.*; P$'e$drot, M.*; Fablet, L.*; 蓬田 匠; Nguyen, T. T.*; Sivry, Y.*; Catrouillet, C.*; Pradas del Real, A. E.*; Choueikani, F.*; Vantelon, D.*; et al.

Environmental Science & Technology, 59(11), p.5747 - 5755, 2025/03

 被引用回数:3 パーセンタイル:92.62(Engineering, Environmental)

クロム(Cr)とマグネタイトの相互作用メカニズムを理解し予測することは、環境中のCrの物地球化学的挙動を解明し、最適な土壌浄化および水処理戦略を開発する上で特に重要である。最も毒性の高いCr(VI)がCr(III)に還元されて除去されることは広く報告されているが、Cr(III)のマグネタイトへの吸着に関わる正確なメカニズムは解明されていなかった。本研究では、Cr(III)溶液と10nmサイズのマグネタイトの相互作用を調べた。本研究では、pHとマグネタイトの化学量論の双方がCr(III)吸着メカニズムに及ぼす複合的な影響を調べることで、Cr(III)-(hydr)Oxide沈殿の生成が必ずしも溶液からのCr(III)の除去を駆動するプロセスではないことが明らかになった。これらの結果は、環境中のCrの輸送と終着点の予測、およびマグネタイトを用いたCr浄化プロセスの開発に役立つと期待される。

論文

A Benchmark for Monte Carlo simulation of photoneutron fields from electron accelerators

Sari, A.*; Meleshenkovskii, I.*; 小川 達彦; Tran, K.-T.*; Jinaphanh, A.*; Jouanne, C.*; Zoia, A.*

Nuclear Instruments and Methods in Physics Research A, 1072, p.170168_1 - 170168_17, 2025/03

電子加速器は非破壊分析や放射線治療など様々な用途で用いられ、中でも10MeV以上のエネルギーの電子線は制動放射を通して光核反応を誘起するため、放射線安全にとって重要な中性子線を発生させる。そうした中性子は系統的な測定データがないが、シミュレーション予測の精度を検証することは重要である。そこで、単色光子の照射を受けた様々な物質から生じる中性子のエネルギー・角度分布を種々の条件で計算・比較することで、シミュレーションの妥当性を検証した。3つの計算コードMCNP、TRIPOLI-4、PHITSにより評価済み核データENDF7uを用いて計算するとともに、PHITSでJENDL-5を使う場合と、PHITS自身の核反応モデルを使う場合で、同様の中性子生成計算結果を比較した。この解析の結果、まずW-184とTa-181のターゲットの場合、ENDF7uによる計算ではどのコードでも中性子エネルギースペクトルに物理的に不合理な凹凸構造が生じた。また、JENDL-5を使った計算では重水とベリリウムがターゲットの場合、保存則に沿わない中性子が生じた。これはPHITSのソースを調査したところ、座標系を重心系から実験室系に変換するPHITSの計算処理の誤りが原因であると判明した。しかしこの修正の後も、中性子の角度分布は運動学的に不合理な点があり、更なる修正が必要であることも分かっている。このように、本研究は光核反応の計算に関して放射線輸送計算コードや評価済み核データの問題点を明らかにし、修正の指針を与えることに貢献した。

論文

Uncertainty quantification for severe-accident reactor modelling; Results and conclusions of the MUSA reactor applications work package

Brumm, S.*; Gabrielli, F.*; Sanchez Espinoza, V.*; Stakhanova, A.*; Groudev, P.*; Petrova, P.*; Vryashkova, P.*; Ou, P.*; Zhang, W.*; Malkhasyan, A.*; et al.

Annals of Nuclear Energy, 211, p.110962_1 - 110962_16, 2025/02

 被引用回数:9 パーセンタイル:96.17(Nuclear Science & Technology)

The completed Horizon-2020 project on "Management and Uncertainties of Severe Accidents (MUSA)" has reviewed uncertainty sources and Uncertainty Quantification methodology for the purpose of assessing Severe Accidents (SA). The key motivation of the project has been to bring the advantages of the Best Estimate Plus Uncertainty approach to the field of Severe Accident. The applications brought together a large group of participants that set out to apply uncertainty analysis (UA) within their field of SA modelling expertise, in particular reactor types, but also SA code used (ASTEC, MELCOR, etc.), uncertainty quantification tools used (DAKOTA, RAVEN, etc.), detailed accident scenarios, and in some cases SAM actions. This paper synthesizes the reactor-application work at the end of the project. Analyses of 23 partners are sorted into different categories, depending on whether their main goal is/are (i) uncertainty bands of simulation results; (ii) the understanding of dominating uncertainties in specific sub-models of the SA code; (iii) improving the understanding of specific accident scenarios, with or without the application of SAM actions; or, (iv) a demonstration of the tools used and developed, and of the capability to carry out an uncertainty analysis in the presence of the challenges faced. The partners' experiences made during the project have been evaluated and are presented as good practice recommendations. The paper ends with conclusions on the level of readiness of UA in SA modelling, on the determination of governing uncertainties, and on the analysis of SAM actions.

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