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論文

Improvement of JASMINE code for ex-vessel molten core coolability in BWR

松本 俊慶; 川部 隆平*; 岩澤 譲; 杉山 智之; 丸山 結

Annals of Nuclear Energy, 178, p.109348_1 - 109348_13, 2022/12

シビアアクシデント時の溶融物関連事象を評価するためにFCIコードであるJASMINEの機能拡張を行った。溶融物の冷却性評価ではキャビティ床面上における粒子状・アグロメレーション・ケーキ状デブリ質量割合や最終的な幾何形状の予測が必要である。アグロメレーションモデルでは、熱を保有した粒子同士のくっつきを考慮し、組み込んだ。もう一つのモデル改良は拡がりモデルの改良である。浅水方程式を導入し、拡がり先端部のクラスト成長に基づく拡がり停止条件を組み込んだ。調整係数の最適化のためにスウェーデンKTHにおいて実施されたDEFOR-A及びPULiMS実験を参照した。JASMINEコードによる実験解析では共通のパラメータセットで良い再現性が得られ、主要な現象は適切にモデル化されたことを示した。

論文

Dynamic probabilistic risk assessment of nuclear power plants using multi-fidelity simulations

Zheng, X.; 玉置 等史; 杉山 智之; 丸山 結

Reliability Engineering & System Safety, 223, p.108503_1 - 108503_12, 2022/07

 被引用回数:3 パーセンタイル:86.32(Engineering, Industrial)

Dynamic probabilistic risk assessment (PRA) more explicitly treats timing issues and stochastic elements of risk models. It extensively resorts to iterative simulations of accident progressions for the quantification of risk triplets including accident scenarios, probabilities and consequences. Dynamic PRA leverages the level of detail for risk modeling while intricately increases computational complexities, which result in heavy computational cost. This paper proposes to apply multi-fidelity simulations for a cost- effective dynamic PRA. It applies and improves the multi-fidelity importance sampling (MFIS) algorithm to generate cost-effective samples of nuclear reactor accident sequences. Sampled accident sequences are paralleled simulated by using mechanistic codes, which is treated as a high-fidelity model. Adaptively trained by using the high-fidelity data, low-fidelity model is used to predicting simulation results. Interested predictions with reactor core damages are sorted out to build the density function of the biased distribution for importance sampling. After when collect enough number of high-fidelity data, risk triplets can be estimated. By solving a demonstration problem and a practical PRA problem by using MELCOR 2.2, the approach has been proven to be effective for risk assessment. Comparing with previous studies, the proposed multi-fidelity approach provides comparative estimation of risk triplets, while significantly reduces computational cost.

論文

In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project

Lind, T.*; Herranz, L. E.*; Sonnenkalb, M.*; 丸山 結

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 15 Pages, 2022/03

The accident progression and fission product release from the three damaged units of the Fukushima Daiichi Nuclear Power Plant were systematically investigated in the OECD/NEA BSAF project phases 1 and 2. As a result of those investigations, a good progress was achieved in establishing defendable accident scenarios and the corresponding fission product releases to the environment. Nonetheless, there are some areas requiring further work, particularly concerning fission product behavior. They are addressed in the OECD/NEA project "Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi NPS" (ARC-F). Based on the outcome of the BSAF project, several focus areas were selected for further investigations in the ARC-F project, one of them being the behavior of fission products and source term. In this paper, five topics which were ranked with a high significance as open issues based on the BSAF project regarding fission product behavior are discussed: i) fission product speciation, ii) iodine chemistry, iii) pool scrubbing, iv) fission product transport and behavior in the buildings, and v) uncertainty analysis and variant calculations. Significant progress has been made in these five topics in the ARC-F project. In this paper, background is given for choosing these topics for specific investigations based on the outcome of the BSAF project. The topics are described and the approach to study them in the ARC-F given along with some exemplary, preliminary results. Finally, the readers' attention is drawn to open issues which are not included in the ARC-F work scope and could need further attention.

論文

Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project

Gupta, S.*; Herranz, L. E.*; Lebel, L. S.*; Sonnenkalb, M.*; Pellegrini, M.*; Marchetto, C.*; 丸山 結; Dehbi, A.*; Suckow, D.*; K$"a$rkel$"a$, T.*

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Pool scrubbing is a major topic in water cooled nuclear reactor technology as it is one of the means for mitigating the source-term to the environment during a severe accident. Pool scrubbing phenomena include coupled interactions between bubble hydrodynamics, aerosols and gaseous radionuclides retention mechanisms under a broad range of thermal-hydraulic conditions as per accident scenarios. Modeling pool scrubbing in some relevant accident scenarios has shown to be affected by substantial uncertainties. In this context, IPRESCA (Integration of Pool scrubbing Research to Enhance Source-term CAlculations) project aims to promote a better integration of international research activities related to pool scrubbing by providing support in experimental research to broaden the current knowledge and database, and by supporting analytical research to facilitate systematic validation and model enhancement of the existing pool scrubbing codes. The project consortium includes more than 30 organisations from 15 countries involving research institutes, universities, TSOs, and industry. For IPRESCA activities, partners join the project with in-kind contributions. IPRESCA operates under NUGENIA Technical Area 2/SARNET (Severe Accident) - Sub Technical Area 2.4 (Source-term). The present paper provides an introduction and overview of the IPRESCA project, including its objectives, organizational structure and the main outcomes of completed activities. Furthermore, key activities currently ongoing or planned in the project framework are also discussed.

論文

Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

島田 亜佐子; 谷口 良徳; 垣内 一雄; 大平 早希; 飯田 芳久; 杉山 智之; 天谷 政樹; 丸山 結

Scientific Reports (Internet), 12(1), p.2086_1 - 2086_11, 2022/02

 被引用回数:0 パーセンタイル:0.01(Multidisciplinary Sciences)

2011年3月12日に福島第一原子力発電所の1号機のベントが行われ、1・2号機共用スタックから放射性ガスが放出された。本研究ではこのベントにより放出された放射性核種の情報を有していると考えられる、1・2号機共用スタック基部のドレンピットから採取したドレン水の放射化学分析を実施した。揮発性の$$^{129}$$Iや$$^{134}$$Cs, $$^{137}$$Csだけでなく、$$^{60}$$Co, $$^{90}$$Sr, $$^{125}$$Sb, 1号機由来安定Moが検出された。1号機由来安定Moの量はCsの量よりもはるかに少ないことから、事故時の炉内状況ではCs$$_{2}$$MoO$$_{4}$$の生成は抑制されたと考えられる。また、2020年10月時点では、約90%のIがI$$^{-}$$、約10%がIO$$_{3}$$$$^{-}$$で存在した。$$^{137}$$Csより多い$$^{129}$$Iが観測されたことから、事故時に$$^{131}$$IはCsIというよりも分子状のヨウ素として放出されたことが示唆された。2011年3月11日に減衰補正した$$^{134}$$Cs/$$^{137}$$Cs放射能比は0.86で、2号機や3号機由来と考えられる放射能比より低いことが示された。

論文

Numerical analysis for FP speciation in VERDON-2 experiment; Chemical re-vaporization of iodine in air ingress condition

塩津 弘之; 伊藤 裕人*; 杉山 智之; 丸山 結

Annals of Nuclear Energy, 163, p.108587_1 - 108587_9, 2021/12

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

In the late phase of severe accident in light water reactor nuclear power station, re-mobilization of fission products (FPs) has a significant impact on the source term because most portion of FPs is retained in reactor coolant system and/or containment vessel. Recently, VERDON-2 experiment showed noticeable re-vaporization, which was one of the re-mobilization phenomena, of iodine under air ingress condition, but this mechanism has not been identified yet. The present study numerically investigated the FPs behaviors in VERDON-2 experiment with the mechanistic FPs transport analysis code incorporating thermodynamic chemical equilibrium model in order to further understand nature for FPs behavior, especially iodine re-vaporization under air ingress condition. Consequently, this analysis reproduced the deposition profile of cesium, one of important FPs in the source term, along the thermal gradient tube (TGT) in the experiment, which revealed that cesium was transported as CsOH in early phase of FP release from fuel, and then formed Cs$$_{2}$$MoO$$_{4}$$ and Cs$$_{2}$$Te after the release of molybdenum and tellurium was activated. Regarding iodine as another important FP, formation of CsI was predicted in steam condition. The CsI was transported and partly deposited and condensed onto the TGTs and other components of the VERDON facility. Under the air ingress condition, the present analysis showed the agreement for iodine re-vaporization in the experiment and revealed its mechanism; the deposits of iodide were chemical re-vaporized as molecular iodine (I$$_{2}$$) gas by redox reaction with competitive elements such as molybdenum, chromium and tellurium.

論文

Improved performance of wide bandwidth neutron-spin polarizer due to ferromagnetic interlayer exchange coupling

丸山 龍治; 山崎 大; 青木 裕之; 阿久津 和宏*; 花島 隆泰*; 宮田 登*; 曽山 和彦; Bigault, T.*; Saerbeck, T.*; Courtois, P.*

Journal of Applied Physics, 130(8), p.083904_1 - 083904_10, 2021/08

 被引用回数:2 パーセンタイル:42.69(Physics, Applied)

Ferromagnetic (FM) interlayer exchange coupling of ion-beam sputtered Fe/Ge multilayers was investigated by off-specular polarized neutron scattering measurements. We observed a monotonously growing correlation of magnetic moments in the out-of-plane direction with decreasing Ge thickness. The results of the Fe/Ge multilayers were used to invoke FM interlayer exchange coupling in a neutron polarizing supermirror in order to extend its bandwidth. Typically, the bandwidth is limited due to a Curie temperature close to room temperature of the thinnest Fe layers with less than 3 nm. We propose a modified layer sequence of the neutron polarizing supermirror, where the minimum Fe thickness was set to 3.5 nm whereas the Ge thickness was reduced. A performance test of the neutron polarizing supermirror showed that the FM interlayer exchange coupling contributed to the presence of the magnetization comparable to the bulk and resulted in a marked extension in the bandwidth.

論文

熱流動とリスク評価,1; リスク評価における熱流動解析の役割

丸山 結; 吉田 一雄

日本原子力学会誌ATOMO$$Sigma$$, 63(7), p.517 - 522, 2021/07

確率論的リスク評価(PRA)は合理的かつ定量的にリスクを評価する強力な手法である。しかしながら、PRAを実践しつつ、得られた結果を分析し、様々な意思決定に活用する上では、多様な分野の専門的な知識や技術,経験を必要とする。原子力施設のリスク評価においては、シビアアクシデントに至る過程やその進展を評価することが不可欠であり、それらに強く関連する熱流動は、PRAにおける重要な専門分野の一つである。本稿では、軽水炉のレベル2PRAにおけるソースターム評価及び再処理施設のシビアアクシデント時ソースターム評価を中心に、リスク評価における熱流動解析の役割について概説する。

論文

Phenomena identification ranking tables for accident tolerant fuel designs applicable to severe accident conditions

Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; 丸山 結; Metcalf, J.*; et al.

NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04

The U.S. Nuclear Regulatory Commission (NRC) is preparing to accept anticipated licensing applications for the commercial use of accident tolerant fuel (ATF) in commercial nuclear power plants in the United States. It is the objective of the NRC to evaluate the effects of ATF designs on severe accident behavior, and to determine potential changes to the NRC severe accident analysis computer codes that would simulate plant conditions using ATFs commensurate with the accuracy in accident analyses involving conventional fuels. This report documents the development of Phenomena Identification and Ranking Tables (PIRTs) for near-term ATFs under severe accident conditions in light water reactors (LWRs). The PIRTs were developed by a panel of experts for various near-term ATF design concepts (i.e., FeCrAl cladding, zirconium alloy cladding coated with chromium, and Cr$$_{2}$$O$$_{3}$$ dopants in uranium dioxide fuels) in addition to the impacts from fuel enrichment and burnup. Panel members also considered the severe accident implications of the longer-term ATF concepts. The main figures-of-merit considered in this ranking process are the amount of fission products released into the containment and the quantity of combustible gases generated during an accident. Special focus is given to whether existing severe accident codes and models would be sufficient as applied to LWRs employing these fuels, and whether additional experimental studies or model development would be warranted.

報告書

「グレーデッドアプローチに基づく合理的な安全確保検討グループ」活動状況中間報告(2019年9月$$sim$$2020年9月)

与能本 泰介; 中島 宏*; 曽野 浩樹; 岸本 克己; 井澤 一彦; 木名瀬 政美; 長 明彦; 小川 和彦; 堀口 洋徳; 猪井 宏幸; et al.

JAEA-Review 2020-056, 51 Pages, 2021/03

JAEA-Review-2020-056.pdf:3.26MB

「グレーデッドアプローチに基づく合理的な安全確保検討グループ」は、原子力科学研究部門、安全・核セキュリティ統括部、原子力施設管理部署、安全研究・防災支援部門の関係者約10名で構成され、機構の施設管理や規制対応に関する効果的なグレーデッドアプローチ(安全上の重要度に基づく方法)の実現を目的としたグループである。本グループは、2019年の9月に活動を開始し、以降、2020年9月末までに、10回の会合を開催するとともに、メール等も利用し議論を行ってきた。会合では、グレーデッドアプローチの基本的考え方、各施設での新規制基準等への対応状況、新検査制度等についての議論を行なうとともに、各施設での独自の検討内容の共有等を行っている。本活動状況報告書は、本活動の内容を広く機構内外で共有することにより、原子力施設におけるグレーデッドアプローチに基づく合理的で効果的な安全管理の促進に役立つことを期待し取りまとめるものである。

論文

原子力機構における原子力安全研究の取り組み; 福島第一原子力発電所事故への対応及び同事故を踏まえた研究の展開を中心に

丸山 結

エネルギーレビュー, 41(4), p.20 - 24, 2021/03

2011年3月に発生した東京電力福島第一原子力発電所事故後に安全研究・防災支援部門が発足し、この中に安全研究センター及び原子力緊急時支援・研修センターが置かれた。安全研究・防災支援部門における最大のミッションは、東京電力福島第一原子力事故の教訓を踏まえつつ、ニーズに則した質の高い安全研究を行って、原子力規制委員会/原子力規制庁を技術的に支援することである。本稿では、東京電力福島第一原子力発電所の事故を踏まえたニーズに対応した安全研究センターにおける研究の展開に加え、安全研究センターにおける東京電力福島第一原子力発電所事故の対応に係わる短期的な(事故発生直後から大よそ1年間)活動及び東京電力福島第一原子力発電所の事故に係わる国際協力について概説する。

論文

Improvement in sputtering rate uniformity over large deposition area of large-scale ion beam sputtering system

丸山 龍治; 山崎 大; 阿久津 和宏*; 花島 隆泰*; 宮田 登*; 青木 裕之; 曽山 和彦

JPS Conference Proceedings (Internet), 33, p.011092_1 - 011092_6, 2021/03

中性子偏極スーパーミラーは、熱及び冷中性子ビームを偏極するための光学素子であり、実機への応用には高偏極率であるとともに必要な外部磁場を小さく抑えること、即ち偏極スーパーミラーを構成する磁気多層膜が磁気的にソフトであることが重要である。本発表では、J-PARC MLFの共用ビームラインBL17等を用いて得られた偏極スーパーミラーの高偏極率化、及び磁気多層膜の軟磁性化を目指しこれを構成する多層膜特有の磁気特性の解明に関する成果について議論する。

論文

Mode distribution analysis for superionic melt of CuI by coherent quasielastic neutron scattering

川北 至信; 菊地 龍弥*; 田原 周太*; 中村 充孝; 稲村 泰弘; 丸山 健二*; 山内 康弘*; 河村 聖子; 中島 健次

JPS Conference Proceedings (Internet), 33, p.011071_1 - 011071_6, 2021/03

ヨウ化銅は高温固相で、ヨウ素イオンが作る面心立方格子の隙間を銅イオンが動く超イオン伝導体になることで知られている。溶融相でも、集団的あるいは協調的なイオンの運動を示す特徴がある。MDシミュレーションにおいて、銅イオンの拡散がヨウ素イオンより非常に速いこと分かっている。Cu-Cu部分構造因子にはFSDPと呼ばれる構造を持ち、銅の分布に中距離秩序があることを示している。さらに、Cu-Cu部分二体分布関数は、Cu-Iで形成される最近接分布に深く入り込んでいる。そうした溶融CuIの異常的振る舞いの原因を解明するために、J-PARCの物質・生命科学実験施設に設置されたディスクチョッパー分光器AMATERASを用いて、中性子準弾性散乱(QENS)実験を行った。構造可干渉性のQENSから得られた動的構造因子を理解するため、モード分布解析を行った。その結果、ヨウ素イオンの運動が局所的に閉じ込められた空間で揺らぐような運動であること、一方銅イオンはヨウ素イオンより速く拡散する運動をしていることが分かった。

論文

A Project focusing on the contamination mechanism of concrete after the accident at Fukushima Daiichi Nuclear Power Plant

山田 一夫*; 丸山 一平*; 芳賀 和子*; 五十嵐 豪*; 粟飯原 はるか; 富田 さゆり*; Kiran, R.*; 大澤 紀久*; 柴田 淳広; 渋谷 和俊*; et al.

Proceedings of International Waste Management Symposia 2021 (WM 2021) (CD-ROM), 10 Pages, 2021/03

To properly decommission the Fukushima Daiichi Nuclear Power Plant, the contamination levels and mechanisms for the concrete structures must be assessed. In this review, we outline the results of this study and present the objectives of a future study called "Quantitative Evaluation of Contamination in Reinforced Concrete Members of Fukushima Daiichi NPP Buildings Considering the Actual Environment Histories for Legitimate Treatments", which will run from October 2020 to March 2023. The experimental results from the first project indicate that concrete carbonation, Ca leaching, and drying conditions affected the adsorption of Cs and Sr and their penetration depths. Additionally, the studies showed that $$alpha$$-nuclides precipitated on the surface of the samples because of the high pH of concrete. A reaction transfer model was developed to further assess the adsorption characteristics of Cs and Sr in carbonated cement paste and concrete aggregates. The model used real concrete characteristics from the FDNPP materials and historical boundary conditions at the site, including radionuclide concentrations and penetration profiles within the turbine pit wall. The water suction by dried concrete was evaluated with the consideration of the structure change of cement hydrates by X-ray CR and $$^{1}$$H-NMR relaxometry. In the new project, the studies will also include concrete cracks for more realistic contamination estimations.

論文

Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF Project

Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.

Nuclear Technology, 206(9), p.1449 - 1463, 2020/09

 被引用回数:23 パーセンタイル:98.46(Nuclear Science & Technology)

The OECD/NEA Benchmark Study at the Accident of Fukushima Daiichi Nuclear Power Station (BSAF) project, which started in 2012 and continued until 2018, was one of the earliest responses to the accident at Fukushima Daiichi. The project, divided into two phases addressed the investigation of the accident at Unit 1, 2 and 3 by Severe Accident (SA) codes until 500 h focusing on thermal-hydraulics, core relocation, Molten Corium Concrete Interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, Reactor Pressure Vessel (RPV) and Primary Containment Vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS signatures. The combination of code results and inspections (muon radiography, PCV inspection) has provided a picture of the current status of the debris distribution and plant status. All units present a large relocation of core materials and all of them present ex-vessel debris with Unit 1 and Unit 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RPV and into cavity floor, RPV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RPV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in detail further aspects of the Fukushima Daiichi accident.

論文

Computational study on the spherical laminar flame speed of hydrogen-air mixtures

Trianti, N.; 茂木 孝介; 杉山 智之; 丸山 結

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 9 Pages, 2020/08

The computational fluid dynamics (CFD) have been developed to analyze the correlation equation for laminar flame speed of hydrogen-air mixtures. This analysis was carried out on the combustion of hydrogen-air mixtures performed at the spherical bomb experiment facility consists of a spherical vessel equipped (563 mm internal diameter). The facility has been designed and built at CNRS-ICARE laboratory. The simulation was carried out using the reactingFoam solver, one of a transient chemical reaction solver in OpenFOAM 5.0. The LaunderSharmaKE model was applied for turbulent flow. The interaction of the chemical reaction with the turbulent flow was taken into account using PaSR (Partial Stirred Reactor) model with 19 elementary reactions for the hydrogen combustion. The initial condition of spherical flame analysis was set so as to be consistent with those of the experiment. The position of the flame front was detected by the steep drop of hydrogen mass fraction in the spherical radii, and the flame propagation velocity was estimated from the time-position relationship. The analysis result showed the characteristic of spherical flame acceleration was qualitatively reproduced even though it has a discrepancy with the experiment. After validating the calculation of spherical experiments, a laminar burning velocity correlation is presented using the same boundary conditions with the variation of hydrogen concentration, temperature, and pressure. The calculation of laminar flame speed of hydrogen-air mixtures by reactingFoam use reference temperature T$$_{rm ref}$$ = 293 K and reference pressure P$$_{rm ref}$$ = 1 atm with validated in the range of hydrogen concentration 6-20%; range of temperature 293-493 K; and range of pressure 1-3 atm.

論文

よくわかるPRA; うまくリスクを使えるために,1; 確率論的リスク評価の技術課題

丸山 結; 喜多 利亘*; 倉本 孝弘*

日本原子力学会誌ATOMO$$Sigma$$, 62(6), p.328 - 333, 2020/06

発電用原子炉施設, 核燃料施設などの原子力関連施設の安全確保において、確率論的リスク評価(PRA)が重要な役割を担っている。PRAより得られる様々な知見や情報が原子力関連施設の運用に関する意思決定に有用であり、自主的安全性向上活動、新検査制度などにおいて、PRAより得られるリスクの活用もなされている。一方で、PRAの評価技術についても、日本原子力学会標準委員会において、PRA手法を中心とした標準(実施基準)の整備を行うなど段階的に進展している。こういった背景の中で、「よくわかるPRA; うまくリスクを使えるために」と題する連載講座を本稿から7回にわたって開講する。第1回は、原子炉施設及び核燃料施設を対象に、内的事象及び外的事象、レベル1, レベル2及びレベル3、各運転状態(通常運転時や停止時)に対するPRAについて、技術の現状及び応用例、今後の技術課題や研究・開発の方向性について概説する。

論文

Effects of surface tension and viscosity on liquid jet breakup

Zhan, Y.*; 桑田 裕介*; 丸山 清嵩*; 大川 富雄*; 榎木 光治*; 青柳 光裕; 高田 孝

Experimental Thermal and Fluid Science, 112, p.109953_1 - 109953_8, 2020/04

 被引用回数:7 パーセンタイル:64.91(Thermodynamics)

The breakup process of liquid jet was explored through visualization to develop a prediction model for liquid splash. Water, ethanol aqueous solution, and glycerin aqueous solution were used as the test liquids to explore the effects of surface tension and viscosity. Since the droplets were produced due to jet breakup, the impact frequency was zero just downstream of the nozzle and increased asymptotically with an increase in the distance from the nozzle. Thus, auxiliary correlations were developed for the minimum breakup length where the jet breakup is initiated, the maximum breakup length where the jet breakup is completed, the mean droplet size and the impact frequency. It was demonstrated that the impact frequencies calculated by the proposed model agree with the experimental data fairly well. For the application to coolant leakage in sodium-cooled fast reactors, a simple method to ensure conservative estimation of the impact frequency was also proposed.

論文

偏極スーパーミラーのさらなる高性能化を目指して

丸山 龍治

波紋, 30(1), p.45 - 50, 2020/02

サイエンスの様々な分野において偏極中性子散乱の果たす役割は益々増大しており、J-PARC MLFでの偏極中性子ビーム利用の高度化のため原子力機構では偏極スーパーミラーの高性能化に関する研究開発を進めている。本稿では、それらの研究において近年得られたいくつかの成果を報告する。

論文

Coherent magnetization rotation of a layered system observed by polarized neutron scattering under grazing incidence geometry

丸山 龍治; Bigault, T.*; Saerbeck, T.*; Honecker, D.*; 曽山 和彦; Courtois, P.*

Crystals (Internet), 9(8), p.383_1 - 383_13, 2019/08

 被引用回数:4 パーセンタイル:48.42(Crystallography)

中性子偏極スーパーミラーを偏極中性子散乱測定に用いる際には、試料の磁化や中性子ビームの偏極率への影響を小さく抑えるために、これを構成する多層膜が磁気的にソフトであることが重要である。これらの多層膜は交換結合長(数十nm)よりも小さい結晶粒から構成され、磁気特性はバルクとは異なり隣り合うスピン間での交換相互作用による結晶磁気異方性の平均化(ランダム異方性モデル)によって理解される。本研究では、多層膜の面内磁気構造の磁場依存性を斜入射偏極中性子散乱を用いて観察することにより、我々の系が本モデルに従うかどうかに関する検証を行った。実験によって得られた散乱データは歪曲波ボルン近似による散乱強度分布シミュレーションにより解析され、磁化の方向が揃った領域は0.5$$sim$$1.1$$mu$$m程度の範囲内で磁化の反転過程において大きく変化しないという結果が得られた、これは、磁化の過程がバルクで見られる磁壁の形成と移動ではなくコヒーレントな磁気モーメントの回転によることを意味する。今後は、このモデルの適応範囲等について研究を進め、多層膜の磁気特性を支配するメカニズムに関する理解を深めることが重要である。

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