Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
熊崎 由衣; 鈴木 悟; 金澤 将士*; 国井 克彦; 米澤 稔; 板橋 慶造*
The Grey Journal; An International Journal on Grey Literature, 15(1), p.45 - 50, 2019/04
原子力機構(JAEA)図書館では会議録や技術レポートを重視して収集している。これらはCD-ROMやUSB等の記録媒体を用いて電子的に刊行されることが増えているが、紙媒体と比較して電子情報の記録媒体の保管可能な年限は短い。たとえばJAEA図書館では1990年代に発行された図書と技術レポートを所蔵しているが、再生機器等の更新に伴って利用できなくなっている資料があり、長期保存や利用環境の維持が課題である。対策としては資料と再生機器のメンテナンス, エミュレーションやマイグレーションが望ましいが、十分にできているとは言い難い。電子情報の長期保存と利用についてJAEA図書館の現状を報告するとともに、公刊された電子媒体情報がGreyになりつつある点について問題提起を行った。
熊崎 由衣; 鈴木 悟; 金澤 将士*; 国井 克彦; 米澤 稔; 板橋 慶造
Proceedings of 20th International Conference on Grey Literature (GL-20), p.99 - 104, 2019/02
原子力機構(JAEA)図書館では会議録や技術レポートを重視して収集している。これらはCD-ROMやUSB等の記録媒体を用いて電子的に刊行されることが増えているが、紙媒体と比較して電子情報の記録媒体の保管可能な年限は短い。たとえばJAEA図書館では1990年代に発行された図書と技術レポートを所蔵しているが、そのうち再生可能なソフトウェアがなく、利用できなくなっているものもあり、長期保存や利用環境の維持が課題である。対策としては資料と再生機器のメンテナンス、エミュレーションやマイグレーションが望ましいが、十分にできているとは言い難い。電子情報の長期保存と利用についてJAEA図書館の現状を報告するとともに、公刊された電子媒体情報がGreyになりつつある点について問題提起をしたい。
Ni from the (
,
) reactionElekes, Z.*; Kripk
, 
*; Sohler, D.*; Sieja, K.*; 緒方 一介*; 吉田 数貴; Doornenbal, P.*; Obertelli, A.*; Authelet, G.*; 馬場 秀忠*; et al.
Physical Review C, 99(1), p.014312_1 - 014312_7, 2019/01
パーセンタイル：100(Physics, Nuclear)(,)反応によるNiの核構造の探索実験を行った。Lenzi, Nowacki, Poves, Sieja相互作用を用いた殻模型計算では実験結果を説明しうる陽子空孔状態が得られており、理論的な断面積計算は実験値とよい一致を与えた。実験で得られたすべての状態を理論的に一意に決定することはできなかったが、過去の実験結果と同様にNi同位体でのZ = 28の大きなshell gapを示す結果が得られた。
小林 徹; 鈴木 伸一; 塩飽 秀啓; 矢板 毅
Progress in Nuclear Science and Technology (Internet), 5, p.74 - 77, 2018/11
特定のアクチノイドを効率的に分離できる抽出剤の開発は、核燃料サイクルにおける分離法や放射性廃棄物の処分方法の開発に関連する重要なテーマである。本研究では、N-alkyl-N-phenyl-1,10-phenanthroline-2-carboxamide (PTA)のランタノイドとの錯形成特性について、単結晶X線構造解析や広域X線吸収微細構造(EXAFS)法などを用いた構造解析に基づいて検討した。その結果、PTAは結晶系でも溶液中でも、ランタノイドに対して2分子が配位すること、2つのフェナントロリン窒素と1つのアミド酸素を介して3座配位子として配位することを明らかにした。また、Eu錯体とNd錯体とでその配位結合距離に僅かな変化が見られたが、その変化はランタノイドのイオン半径の違いに対応しており、イオンサイズの僅かな違いは配位特性に大きな影響は及ぼさないことが示された。
鈴木 智也*; 尾形 剛志*; 田中 幹也*; 小林 徹; 塩飽 秀啓; 矢板 毅; 成田 弘一*
Metals, 8(7), p.558_1 - 558_10, 2018/07
被引用回数：1 パーセンタイル：52.95(Materials Science, Multidisciplinary)白金族元素の精製は主に溶媒抽出法によって行われるが、Ruは蒸留によってRuO
として回収される。この蒸留による方法を抽出法に置き換えることができれば、精製プロセスの簡素化が期待される。本研究では、Ruの効率的な抽出法を開発することを目的に、Ruの塩酸中での化学種についてUV-vis分光およびEXAFS法で分析し、N-2-ethylhexyl-bis(N-di-2-ethylhexyl-ethylamide) amine (EHBAA)によって抽出されたRuの特性を調査した。その結果、塩酸濃度が0.5から10MにおけるRuの主たる化学種は、塩酸濃度の上昇に伴って[RuCl(H
O)]
から[RuCl
]
へと変化することが明らかとなった。また、EHBAAによるRuの抽出率は塩酸濃度の上昇に伴って増加し、塩酸濃度が5Mで最大に達し、さらに塩酸濃度が上昇すると抽出率は下降に転ずる。抽出錯体のEXAFS分析の結果からは、Ru
の内圏には5つのClと1つのHOが存在することが示された。さらに塩酸濃度が増加したときのEHBAAによるRuの抽出率の変化と[RuCl
(HO)]
の分布曲線がよく似ていることから、EHBAAは[RuCl(HO)]を抽出すると考えられる。
Sn strand during cooling諏訪 友音*; 辺見 努*; 齊藤 徹*; 高橋 良和*; 小泉 徳潔*; Luzin, V.*; 鈴木 裕士; Harjo, S.
IEEE Transactions on Applied Superconductivity, 28(3), p.6001104_1 - 6001104_4, 2018/04
NbSn strands, whose properties are very sensitive to stress/strain, are utilized for ITER cable-in-conduit conductor (CICC) of the central solenoids. The NbSn strands experience temperature range of 
1000 K from the temperature of the heat treatment with the initiation of the NbSn reaction to the operation temperature of 4 K. Due to this large temperature range, large thermal strain is induced in the NbSn filaments due to the differences between the coefficients of thermal expansion and Young's moduli of the components of the strand. Therefore, it is considered that initial performance of the CICC is influenced by the thermal strain on the NbSn, and it is important to evaluate the strain state of the NbSn strand at low temperature. In this study, the thermal strain of the components of free NbSn strand was measured by neutron diffraction and stress/strain state was assessed from room temperature to low temperature. As the results of diffraction measurements, it was found that 0.111 % and 0.209 % compressive strain were generated in NbSn filaments at 300 and 10 K, respectively.
Shamsuzzaman, M.*; 堀江 達郎*; 浮池 亮太*; 神山 基紀*; 森岡 徹*; 松元 達也*; 守田 幸路*; 田上 浩孝; 鈴木 徹*; 飛田 吉春
Annals of Nuclear Energy, 111, p.474 - 486, 2018/01
被引用回数：2 パーセンタイル：16.17(Nuclear Science & Technology)Particle bed characteristics are experimentally investigated for the sedimentation and subsequent bed formation of solid particles, related to the coolability aspects in core-disruptive accidents. Presently a series of experiments with gravity driven discharge of solid particles into a quiescent water pool was performed to evaluate bed formation characteristic in the course of particle sedimentation. We evaluated the effects of the crucial factors: nozzle diameter, particle density, particle diameter and nozzle height on four key quantitative parameters of bed shape: mound dimple area, mound dimple volume, repose angle and mound height to illustrate the role of the crucial factors on forming the particle bed shape. The investigated crucial factors exhibit a significant role that diversifies the particle bed formation process. Based on the data obtained in the experimental observations, we developed an empirical correlation to compare the predicted results with the experimental bed heights. The proposed empirical correlation can reasonably demonstrate the general trend of the experimental bed height. This correlation could be useful to assess the particle bed elevation, and to identify the governing parameters.
Sheikh, Md. A. R.*; Son, E.*; 神山 基紀*; 森岡 徹*; 松元 達也*; 守田 幸路*; 松場 賢一; 神山 健司; 鈴木 徹*
Journal of Nuclear Science and Technology, 55(6), p.623 - 633, 2018/01
パーセンタイル：100(Nuclear Science & Technology)高速炉の炉心損傷事故時に形成される燃料デブリの堆積高さは、燃料デブリの冷却性及び臨界特性に影響する重要な要因の一つである。本研究では、燃料デブリの堆積挙動に関する実験データベースを構築するため、燃料デブリを模擬した特性(粒子径,密度,球形度等)の異なる固体粒子(アルミナ,スティール)の混合粒子を水プール中へ落下・堆積させる実験を行い、粒子ベッドの堆積高さを測定するとともに、均質粒子及び混合粒子から成るデブリベッドの堆積高さを予測する実験相関式を構築した。構築した実験相関式は粒子ベッドの堆積高さの測定結果と良く一致することを確認した。
中島 健次; 川北 至信; 伊藤 晋一*; 阿部 淳*; 相澤 一也; 青木 裕之; 遠藤 仁*; 藤田 全基*; 舟越 賢一*; Gong, W.*; et al.
Quantum Beam Science (Internet), 1(3), p.9_1 - 9_59, 2017/12
J-PARC物質・生命科学実験施設の中性子実験装置についてのレビューである。物質・生命科学実験施設には23の中性子ビームポートがあり21台の装置が設置されている。それらは、J-PARCの高性能な中性子源と最新の技術を組み合わせた世界屈指の実験装置群である。このレビューでは、装置性能や典型的な成果等について概観する。
生島 一樹*; 柴原 正和*; 西川 聡*; 古川 敬*; 秋田 貢一; 鈴木 裕士; 諸岡 聡
E-Journal of Advanced Maintenance (Internet), 9(3), p.NT87_1 - NT87_5, 2017/11
In this work, an analysis system that can analyze the modification of the residual stress distribution by peening is proposed based on IEFEM. In the proposed analysis system, IEFEM is extended to consider the dynamic effect to analyze the dynamic phenomenon with an impulsive load. The impulsive load due to the collision of shots is modeled as an equivalent load model. The equivalent load model is integrated with IEFEM considering the dynamic effect to calculate spatially and temporally random load in dynamic analyses. Using the proposed analysis system, the residual stress distribution modification by shot peening in a multi-pass welded pipe joint is predicted. The residual stress distributions obtained by the analysis are compared with those measured by X-ray diffraction (XRD), and the effect of the number of shot collisions on the change in residual stress distribution is discussed.
=28 and 
=50; Spectroscopy of 
ZnShand, C. M.*; Podoly
k, Zs.*; Grska, M.*; Doornenbal, P.*; Obertelli, A.*; Nowacki, F.*; Otsuka, T.*; Sieja, K.*; Tostevin, J. A.*; Tsunoda, T.*; et al.
Physics Letters B, 773, p.492 - 497, 2017/10
被引用回数：8 パーセンタイル：14.67(Astronomy & Astrophysics)Low-lying states in neutron-rich 
Zn nuclei were measured for the first time via in-beam 
-ray spectroscopy at RIKEN. These include the 4
to 2 in 
Zn and the 2 to 0 and 4 to 2 in 
Zn. The reduced E(
) energies and increased E(4)/E(2) ratios at =52,54 compared to 
Zn attest that the magicity is confined just on the neutron number =50 only. The levels observed in Zn suggest the onset of deformation towards heavier Zn isotopes. The data were compared to state-of-the-art shell model calculations.
伊藤 大介*; Rivera, M. N.*; 齊藤 泰司*; 青柳 光裕; 神山 健司; 鈴木 徹*
Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 10 Pages, 2017/09
Two-phase flow through porous media must be well understood to develop a severe accident analysis code not only for light water reactor (LWR) but also sodium-cooled fast reactor (SFR). When a core disruptive accident occurs in SFR, the fuel inside the core become melted and interacts with the coolant. As a result, gas-liquid two-phase flow will be formed in the debris bed, which may have porous nature depending on the cooling process. Thus, as first step, the present work focuses on the characteristics of pressure drop in two-phase flows in different porous media conditions (porous size, liquid and gas flow velocity). To construct an experimental database, the measured pressure drop under different conditions was compared with existing correlations. In addition, X-ray radiography, which is very helpful to understand the two-phase structure inside the porous media, was applied to measure porosity and void fraction distribution in the packed bed of spheres.
河田 凌*; 大原 陽平*; Sheikh, Md. A. R.*; Liu, X.*; 松元 達也*; 守田 幸路*; Guo, L.*; 神山 健司; 鈴木 徹
Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 14 Pages, 2017/09
Numerical simulations of various thermal-hydraulic phenomena with multiphase and multicomponent flows in postulated core disruptive accidents (CDAs) are regarded as particular difficulties in the safety analysis of liquid-metal cooled reactors. In a material relocation phase of CDAs, core debris may settle on the core-support structure and/or in the lower inlet plenum of the reactor vessel and then form the debris bed. In particular, the shape of debris bed is crucial for the relocation of molten core and heat-removal capability of the debris bed as well as re-criticality. In the present study, a hybrid numerical simulation method, which couples the multi-fluid model of the 3D fast reactor safety analysis code SIMMER-IV with the discrete element method (DEM), was applied to analyze sedimentation and bed formation behaviors of core debris. In the present study, 3D simulations were performed for a series of particle sedimentation experiments with gravity driven discharge of solid particles into a quiescent cylindrical water pool. The present simulation predicts the sedimentation behavior of mixed particles with different density or particle size as well as homogeneous particles. The simulation results on bed shapes and particle distribution in the bed agree well with the experimental ones. They demonstrate the fundamental applicability of the present hybrid method to solid-particle sedimentation and bed formation simulations.
Nava, M.*; 伊藤 大介*; 齊藤 泰司*; 青柳 光裕; 神山 健司; 鈴木 徹*
Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 5 Pages, 2017/07
Two-phase flow through porous media should be well understood to develop a severe accident analysis code not only for light water reactor but also sodium cooled fast reactor (SFR). When a core disruptive accident occurs in SFR, the fuel inside the core become melted and interacts with the coolant. As a result, gas-liquid two-phase flow will be formed in the debris bed, which may have porous nature depending on the cooling process. Thus, as first step, the present work focuses on the characteristics of pressure drop in single and two-phase flows in different porous media conditions (porous size, liquid and gas flow velocity). In addition, in order to construct an experimental database, the measured pressure drop under different conditions was compared with existing correlations.
小野田 雄一; 松場 賢一; 飛田 吉春; 鈴木 徹
Mechanical Engineering Journal (Internet), 4(3), p.16-00597_1 - 16-00597_14, 2017/06
For the prototype sodium-cooled fast reactor, MONJU, the mechanical energy and structural response under energetics caused by neutronic power excursion during Unprotected Loss of Flow accident (ULOF) were preliminarily analyzed. The objective of this study is to demonstrate the integrity of the reactor vessel against the mechanical load induced by the energetics. Conservative energy production was assumed in order to confirm the robustness of the safety design of MONJU. Mechanical energy was evaluated with the code in which mechanistic modelling of core expansion was implemented. The mechanical energy, which were obtained by analyzing the expanding behavior of core materials after energetics, were about one order of magnitude below the thermodynamic work potential calculated by assuming isentropic expansion of the fuel vapor to one atmosphere, which was often used as an indicator to express the severity of the energetics. Structural integrity was then evaluated with coupled fluid-structure dynamics code using the obtained mechanical energy. No or very small circumferential residual strain of the reactor vessel was evaluated in most analytical cases, and even in the most conservative energy production case, the residual strain was only 0.008 % so that the integrity of the reactor vessel is maintained. The result obtained in the present study shows that MONJU has enough robustness against the mechanical load under energetics.
伊藤 大介*; Nava, M.*; 齊藤 泰司*; 青柳 光裕; 神山 健司; 鈴木 徹*
Proceedings of 2017 Japan-US Seminar on Two-Phase Flow Dynamics (JUS 2017), 4 Pages, 2017/06
Two-phase flow through porous media should be well understood to develop a severe accident analysis code not only for light water reactor but also sodium-cooled fast reactor (SFR). When a core disruptive accident occurs in SFR, the fuel inside the core become melted and interacts with the coolant. As a result, gas-liquid two-phase flow will be formed in the debris bed, which may have porous nature depending on the cooling process. Thus, as first step, the present work focuses on the characteristics of pressure drop in two-phase flows in different porous media conditions (porous size, liquid and gas flow velocity). In addition, to construct an experimental database, the measured pressure drop under different conditions was compared with existing correlations.
山野 秀将; 鈴木 徹; 神山 健司; 工藤 勇*
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 11 Pages, 2017/06
本報は、我が国で設計されている第4世代ナトリウム冷却高速炉(750MWe級)における炉心損傷事故での溶融炉心の炭化ホウ素(B
C)とステンレス鋼(SS)の共晶反応及び移動挙動の重要性を示すとともに、それらの挙動に着目した1500
Cを超える高温条件下での可視化基礎実験について発表する。まず、予想される挙動を考慮して厳密摂動計算ツールを用いて反応度推移を計算し、BC-SS共晶生成物移動挙動が大きな不確かさを持っており反応度推移のうえで重要であることを示した。この挙動を明らかにするため、高温加熱炉の中に溶融SSをBCペレットに接触させ、その反応を可視化する基礎実験を実施した。その実験により、共晶反応を可視化するとともに、固化した試験体の上部で密度分離によりBC-SS共晶生成物が固化・移動した様子が示された。
秋田 貢一; 柴原 正和*; 生島 一樹*; 西川 聡*; 古川 敬*; 鈴木 裕士; Harjo, S.; 川崎 卓郎; Vladimir, L.*
溶接学会論文集(インターネット), 35(2), p.112s - 116s, 2017/06
Residual stresses near the weld metal of the joints before and after a thermal cycle were measured using a reactor based neutron diffraction technique in room temperature. In-situ residual stress measurements were performed on the plate type sample using a pulsed neutron diffraction technique under thermal cycles. Residual stress behaviors of the samples were examined also by the idealized explicit FEM (IEFEM), which agreed well with the experimental results of the residual stress behaviors during thermal cycles. Thermal stresses were induced near the weld metal by the difference of the linear expansion coefficients of the dissimilar base metals. Since the thermal stress exceeded the yield stress of the material during the first heating process, the residual stresses near the weld metal were redistributed and a part of the residual stress was relaxed.
生島 一樹*; 木谷 悠二*; 柴原 正和*; 西川 聡*; 古川 敬*; 秋田 貢一; 鈴木 裕士; 諸岡 聡
溶接学会論文集(インターネット), 35(2), p.75s - 79s, 2017/06
In this research, to investigate the effect of shot peening on operation, an analysis method to predict the behavior of stress distribution on shot peening was proposed. In the proposed system, the load distribution on the collision of shots was modeled, and it was integrated with the dynamic analysis method based on the Idealized explicit FEM (IEFEM). The thermal elastic plastic analysis method using IEFEM was applied to the analysis of residual stress distribution of multi-pass welded pipe joint. The computed residual stress distribution was compared with the measured residual stress distribution using X-ray diffraction (XRD). As a result, it was shown that the both welding residual stress distribution agree well with each other. Considering the computed welding residual stress distribution, the modification of stress distribution due to shot peening was predicted by the proposed analysis system.
生島 一樹*; 柴原 正和*; 秋田 貢一; 鈴木 裕士; 諸岡 聡; 西川 聡*; 古川 敬*
Welding in the World, 61(3), p.517 - 527, 2017/05
本研究では、先ず、ショットピーニングプロセスにおける残留応力の挙動を予測するための解析手法を提案した。この手法ではショットの衝突時の荷重分布をモデル化し、さらに、理想化陽解法FEM解析手法(IEFEM)に基づく動的解析法と組み合わせた。提案した解析システムの解析精度は、ショット一発が衝突した際の応力分布をABAQUSによる解析結果と比較することで確認した。IEFEMを用いて熱弾塑性解析を実施し、配管のマルチパス溶接における溶接残留応力の解析を実施し、解析結果をX線回折による残留応力測定結果と比較し、両者がよく一致することを確認した。次いで、ショットピーニングによる溶接残留応力の変化を提案システムによって解析した。その結果、多量のショットを衝突した場合の残留応力は、解析と実験とでよく一致した。
