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A Numerical investigation on the heat transfer and turbulence production characteristics induced by a swirl spacer in a single-tube geometry under single-phase flow condition

安部 諭; 岡垣 百合亜; 佐藤 聡; 柴本 泰照

Annals of Nuclear Energy, 159, p.108321_1 - 108321_12, 2021/09

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

Heat transfer in the rod bundle is augmented by the mixing vanes on the spacer grid. We conducted a computational fluid dynamics (CFD) simulation with three isotropic turbulence models - standard $$kappa$$-epsilon, realizable $$kappa$$-epsilon, and SST $$kappa$$-omega models - to investigate the relationship between heat transfer and turbulence behaviors downstream a simulant spacer (with four vanes) in a single tube under single-phase flow conditions. Quantitatively, the predicted heat transfer coefficient (HTC), secondary flow intensity, and turbulence intensity with the SST $$kappa$$-omega model displayed a better agreement (than the other isotropic models) with the correlation based on previous studies. Furthermore, the turbulence production was localized in the near-spacer region (z/D $$<$$ 10, where D is the inner diameter), which corresponds with the HTC argumentation region. These results indicate that examining the turbulence production when discussing the HTC augmentation downstream the spacer is essential.


Dimensional reduction by geometrical frustration in a cubic antiferromagnet composed of tetrahedral clusters

大熊 隆太郎*; 古府 麻衣子; 浅井 晋一郎*; Avdeev, M.*; 幸田 章宏*; 岡部 博孝*; 平石 雅俊*; 竹下 聡史*; 小嶋 健児*; 門野 良典*; et al.

Nature Communications (Internet), 12(1), p.4382_1 - 4382_7, 2021/07

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

Dimensionality is a critical factor in determining the properties of solids and is an apparent built- in character of the crystal structure. However, it can be an emergent and tunable property in geometrically frustrated spin systems. Here, we study the spin dynamics of the tetrahedral cluster antiferromagnet, pharmacosiderite, via muon spin resonance and neutron scattering. We find that the spin correlation exhibits a two-dimensional characteristic despite the isotropic connectivity of tetrahedral clusters made of spin 5/2 Fe$$^{3+}$$ ions in the three-dimensional cubic crystal, which we ascribe to two-dimensionalisation by geometrical frustration based on spin wave calculations. Moreover, we suggest that even one-dimensionalisation occurs in the decoupled layers, generating low-energy and one-dimensional excitation modes, causing large spin fluctuation in the classical spin system.


Research and examination of seismic safety evaluation and function maintenance for important equipment in nuclear facilities

古屋 治*; 藤田 聡*; 牟田 仁*; 大鳥 靖樹*; 糸井 達哉*; 岡村 茂樹*; 皆川 佳祐*; 中村 いずみ*; 藤本 滋*; 大谷 章仁*; et al.

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 6 Pages, 2021/07



Status of LBE study and experimental plan at JAEA

斎藤 滋; Wan, T.*; 大久保 成彰; 大林 寛生; 渡辺 奈央; 大平 直也*; 木下 秀孝; 八巻 賢一*; 北 智士*; 吉元 秀光*; et al.

JPS Conference Proceedings (Internet), 33, p.011041_1 - 011041_6, 2021/03



東海再処理施設周辺の環境放射線モニタリング結果; 2019年度

中野 政尚; 藤井 朋子; 根本 正史; 飛田 慶司; 瀬谷 夏美; 西村 周作; 細見 健二; 永岡 美佳; 横山 裕也; 松原 菜摘; et al.

JAEA-Review 2020-069, 163 Pages, 2021/02


核燃料サイクル工学研究所では、「日本原子力研究開発機構核燃料サイクル工学研究所再処理施設保安規定、第IV編 環境監視」に基づき、再処理施設周辺の環境放射線モニタリングを実施している。本報告書は、2019年4月から2020年3月までの間に実施した環境放射線モニタリングの結果、及び大気、海洋への放射性物質の放出に起因する周辺公衆の線量算出結果について、取りまとめたものである。なお、上記の環境放射線モニタリングの結果において、2011年3月に発生した東京電力(2016年4月1日付けで東京電力ホールディングスに変更)福島第一原子力発電所事故で放出された放射性物質の影響が多くの項目でみられた。また、環境監視計画の概要、測定方法の概要、測定結果及びその経時変化、気象統計結果、放射性廃棄物の放出状況、平常の変動幅の上限値を超過した値の評価について付録として収録した。


Density stratification breakup by a vertical jet; Experimental and numerical investigation on the effect of dynamic change of turbulent Schmidt number

安部 諭; Studer, E.*; 石垣 将宏; 柴本 泰照; 与能本 泰介

Nuclear Engineering and Design, 368, p.110785_1 - 110785_14, 2020/11

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

The hydrogen behavior in a nuclear containment vessel is one of the significant issues raised when discussing the potential of hydrogen combustion during a severe accident. Computational Fluid Dynamics (CFD) is a powerful tool for better understanding the turbulence transport behavior of a gas mixture, including hydrogen. Reynolds-averaged Navier-Stokes (RANS) is a practical-use approach for simulating the averaged gaseous behavior in a large and complicated geometry, such as a nuclear containment vessel; however, some improvements are required. We implemented the dynamic modeling for $$Sc_{t}$$ based on the previous studies into the OpenFOAM ver 2.3.1 package. The experimental data obtained by using a small scale test apparatus at Japan Atomic Energy Agency (JAEA) was used to validate the RANS methodology. Moreover, Large-Eddy Simulation (LES) was performed to phenomenologically discuss the interaction behavior. The comparison study indicated that the turbulence production ratio by shear stress and buoyancy force predicted by the RANS with the dynamic modeling for $$Sc_{t}$$ was a better agreement with the LES result, and the gradual decay of the turbulence fluctuation in the stratification was predicted accurately. The time transient of the helium molar fraction in the case with the dynamic modeling was very closed to the VIMES experimental data. The improvement on the RANS accuracy was produced by the accurate prediction of the turbulent mixing region, which was explained with the turbulent helium mass flux in the interaction region. Moreover, the parametric study on the jet velocity indicates the good performance of the RANS with the dynamic modeling for $$Sc_{t}$$ on the slower erosive process. This study concludes that the dynamic modeling for $$Sc_{t}$$ is a useful and practical approach to improve the prediction accuracy.


LES-WALE simulation on two liquid mixing in the horizontal legs and downcomer; The Open-test condition in the TAMU-CFD benchmark (IBE-5)

安部 諭; 岡垣 百合亜; 石垣 将宏; 柴本 泰照

Proceedings of OECD/NEA Workshop on Virtual CFD4NRS-8; Computational Fluid Dynamics for Nuclear Reactor Safety (Internet), 11 Pages, 2020/11

The fifth international benchmark exercise (IBE-5), the cold-leg mixing CFD benchmark, was conducted under the support of OECD/NEA. The experiment for IBE-5 was designed to visualize the mixing phenomena of two liquids with different density in a horizontal leg (as a simulant of the cold-leg) and downcomer. This paper shows our CFD result on the open test condition in IBE-5. We selected the Large-eddy simulation (LES) solving the filtered equation of flow and concentration fields. Regarding the eddy-viscosity to model the turbulence flux of the momentum at sub-grid scale (SGS), Wall-adapting locale eddy-viscosity (WALE) model, a modified version from the Smagorinsky model, was applied. The experimental geometry was resolved with three different numerical mesh systems. The CFD analysis predicted the laminar-like flow behavior in the horizontal leg. Due to the large density difference between the two liquids, the turbulence production was suppressed strongly, and the velocity fluctuation in the horizontal leg became very slow and small. In contrast, the strong turbulence mixing in the downcomer was predicted. The plume from the horizontal leg entrained with the surroundings and spread circumferentially in the downcomer. The comparison with the TAMU experimental data reveals the good performance of the WALE model. In addition, we discuss the appearance characteristics of the high concentration of the heavy liquid in the downcomer in the LES. The Probability Density Function (PDF) and Cumulative Distribution Function (CDF) are derived based on the predicted time-series of the heavy liquid concentration. The PDF around the mean concentration in the case with the low mesh resolution is larger than that predicted by the higher resolution due to the excessive homogenization of the heavy fluid concentration. This study reveals the importance to note the required mesh resolution to predict the appearance event of the high concentration.


Numerical study on bubble hydrodynamics with flow transition for pool scrubbing

岡垣 百合亜; 柴本 泰照; 安部 諭

Proceedings of OECD/NEA Workshop on Virtual CFD4NRS-8; Computational Fluid Dynamics for Nuclear Reactor Safety (Internet), 12 Pages, 2020/11

A bubbly flow with a single injection orifice is numerically analyzed for pool scrubbing phenomena using different computational fluid dynamics (CFD) methodologies. The calculation covers the total regime of pool scrubbing from air injection to bubble swarm through the transition region. Such two-phase flow behaviors strongly affect particle removal in a bubble. The experimental bubbles are known to be oblate spherical and exhibit secondary motion, including path instability and shape oscillations. Moreover, bubbles in a swarm are subject to coalescence and breakup. While these may well affect bubble internal heat/mass transfer and particle capture, no established way is available for considering such influences in practical calculations. Pool scrubbing code SPARC-90 uses an oblate spherical bubble model but assumes a steady, rectilinear bubble rise without secondary motion. The 3-D CFD has the potential to capture the bubble interaction in the swarm region in detail. In the present study, the experiment by Abe et al. (Nuclear Engineering and Design 337, 2018) was referred for the calculation, and their data were used to validate if the CFD simulation can predict the flow transition accurately. Two types of solvers based on the volume of fluid (VOF) method and the simple coupled volume of fluid with level set (S-CLSVOF) method are used for the interface capture. The two solvers were validated by comparing with the experimental results. As a result, the void fraction profiles along the vertical central axis were in good agreement with the experimental data, regardless of the solvers, and those along horizontal lines in a central plane slightly improved with the S-CLSVOF method by the more accurate calculation of the surface tension.


Experimental investigation of density stratification behavior during outer surface cooling of a containment vessel with the CIGMA facility

石垣 将宏; 安部 諭; 柴本 泰照; 与能本 泰介

Nuclear Engineering and Design, 367, p.110790_1 - 110790_15, 2020/10

 被引用回数:3 パーセンタイル:39.17(Nuclear Science & Technology)

シビアアクシデント時の格納容器(CV)内の流体や構造物を冷却するための有効なアクシデントマネジメントとして、CVの外面冷却が期待されている。一方、以下のような可能性も考えられる。第一に、シビアアクシデント時に水-ジルコニウム反応により水素ガスが発生し、外表面冷却により水素を含む非凝縮性ガスが蓄積し、密度成層が形成される可能性がある。第二に、非凝縮性ガスの蓄積は熱伝達を低下させ、CVの冷却を阻害する可能性がある。これらの課題については、これまで多くの研究が行われてきた。しかし、外表面冷却によって生じる密度成層挙動や成層崩壊の条件に着目した体系的な検討は十分に行われていない。また、水素の蓄積による伝熱劣化を定量的に評価していない。そこで、実験設備CIGMA(Containment InteGral effects Measurement Apparatus)を構築し、CIGMA設備を用いて容器外面冷却時の格納容器熱流動挙動の実験的研究を行った。さらに、安定な密度成層が維持できる条件を考慮することで、自然対流が密度成層化挙動に与える影響を議論した。


Application of immersed boundary method for jet flow in grating type structure

廣瀬 意育; 石垣 将宏; 安部 諭; 柴本 泰照

Proceedings of International Topical Meeting on Advances in Thermal Hydraulics (ATH '20) (Internet), p.757 - 767, 2020/10

This paper describes an application of an immersed boundary method (IBM) to internal structure in a containment vessel as a means to reduce the modeling cost for accident analysis. A brinkman penalization method, that is one of the IBMs, is selected and implemented in OpenFOAM code. The calculation is performed for a grating-type structure in a rectangular vessel and an upward jet flow impinging on the grating is analyzed. The IBM is an appealing approach for solving flow passing complex geometry, whereas a very complicated body fitted mesh with fine resolution might be required in a conventional CFD approach. The results were compared with experimental data of flow velocity distribution through the grating measured by Particle Image Velocimetry technique. The flow immediately downstream of the grating is characterized by multimodal profile with intervals determined by a lattice width of the grating. This multimodal flow merges into one with unimodal shape in the downstream far from the grating. The present analysis reproduced the distinctive flow structure observed in the experiment. The model predicted a serrated profile consistent with the experimental results and this could be reproduced even with a relatively regular computational mesh compared to the traditional method.


Unsteady natural convection in a cylindrical containment vessel (CIGMA) with external wall cooling; Numerical CFD simulation

Hamdani, A.; 安部 諭; 石垣 将宏; 柴本 泰照; 与能本 泰介

Energies (Internet), 13(14), p.3652_1 - 3652_22, 2020/07

 被引用回数:0 パーセンタイル:0(Energy & Fuels)

In the case of a severe accident, natural convection plays an important role in the atmosphere mixing of nuclear reactor containments. In this case, the natural convection might not in the steady-state condition. Hence, instead of steady-state simulation, the transient simulation should be performed to understand natural convection in the accident scenario within a nuclear reactor containment. The present study, therefore, was aimed at the transient 3-D numerical simulations of natural convection of air around a cylindrical containment with unsteady thermal boundary conditions (BCs) at the vessel wall. For this purpose, the experiment series was done in the CIGMA facility at Japan Atomic Energy Agency (JAEA). A 3-D model was simulated with OpenFOAM, applying the unsteady Reynolds-averaged Navier-Stokes equations (URANS) model. Different turbulence models were studied, such as the standard k-$$varepsilon$$, standard k-$$omega$$, k-$$omega$$ shear stress transport (SST), and low-Reynolds-k-$$varepsilon$$ Launder-Sharma. The results of the four turbulence models were compared versus the results of experimental data.


Assessment model of radiation doses from external exposure to the public after the Fukushima Daiichi Nuclear Power Plant accident

高原 省五; 飯島 正史*; 渡邊 正敏*

Health Physics, 118(6), p.664 - 677, 2020/06

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



Spallation and fragmentation cross sections for 168 MeV/nucleon $$^{136}$$Xe ions on proton, deuteron, and carbon targets

Sun, X. H.*; Wang, H.*; 大津 秀暁*; 櫻井 博儀*; Ahn, D. S.*; 合川 正幸*; 福田 直樹*; 磯部 忠昭*; 川上 駿介*; 小山 俊平*; et al.

Physical Review C, 101(6), p.064623_1 - 064623_12, 2020/06

 被引用回数:2 パーセンタイル:35.83(Physics, Nuclear)

理化学研究所RIビームファクトリーにて逆運動学法を使用し、核子当たり168MeVの陽子, 重陽子, 炭素イオン入射による$$^{136}$$Xeのスポレーションおよびフラグメンテーション反応からの同位体生成断面積を測定した。炭素イオンの場合は全運動エネルギーが高くなるため、質量数の小さな同位体の生成断面積が大きくなった。また、今回新たに測定されたデータを以前により高い入射エネルギーで測定されたデータと比較することで、同位体生成断面積の入射エネルギー依存性を調査した。さらに、測定データをPHITS, SPACS, EPAX, DEURACSの計算値と比較した。本研究で測定したデータは、理論計算の良いベンチマークになると考えられる。


How different is the core of $$^{25}$$F from $$^{24}$$O$$_{g.s.}$$ ?

Tang, T. L.*; 上坂 友洋*; 川瀬 頌一郎; Beaumel, D.*; 堂園 昌伯*; 藤井 俊彦*; 福田 直樹*; 福永 拓*; Galindo-Uribarri. A.*; Hwang, S. H.*; et al.

Physical Review Letters, 124(21), p.212502_1 - 212502_6, 2020/05

 被引用回数:9 パーセンタイル:88.96(Physics, Multidisciplinary)

中性子過剰核$$^{25}$$Fの構造が($$p,2p$$)反応で調査した。$$pi 0d_{5/2}$$軌道の分光学的因子は1.0$$pm$$0.3と大きいが、一方で残留核である$$^{24}$$Oが基底状態である割合は約35%,励起状態は約0.65%であることが明らかになった。この結果は、$$^{25}$$Fのコア核$$^{24}$$Oは基底状態とは大きく異なり、$$^{24}$$Oの$$0d_{5/2}$$軌道に陽子がひとつ加わることで$$^{24}$$Oと$$^{25}$$Fの中性子軌道が相当に変化していると推測される。これは酸素同位体ドリップライン異常のメカニズムである可能性がある。


東海再処理施設周辺の環境放射線モニタリング結果; 2018年度

中野 政尚; 藤井 朋子; 根本 正史; 飛田 慶司; 河野 恭彦; 細見 健二; 西村 周作; 松原 菜摘; 前原 勇志; 成田 亮介; et al.

JAEA-Review 2019-048, 165 Pages, 2020/03


核燃料サイクル工学研究所では、「日本原子力研究開発機構核燃料サイクル工学研究所再処理施設保安規定、第IV編 環境監視」に基づき、再処理施設周辺の環境放射線モニタリングを実施している。本報告書は、2018年4月から2019年3月までの間に実施した環境放射線モニタリングの結果、及び大気、海洋への放射性物質の放出に起因する周辺公衆の線量算出結果について、取りまとめたものである。なお、上記の環境放射線モニタリングの結果において、2011年3月に発生した東京電力(2016年4月1日付けで東京電力ホールディングスに変更)福島第一原子力発電所事故で放出された放射性物質の影響が多くの項目でみられた。また、環境監視計画の概要、測定方法の概要、測定結果及びその経時変化、気象統計結果、放射性廃棄物の放出状況、平常の変動幅の上限値を超過した値の評価について付録として収録した。


Anomalous radioisotope production for $$^{68}$$ZnO using polyethylene by accelerator neutrons

塚田 和明; 永井 泰樹*; 橋本 慎太郎; 湊 太志; 川端 方子*; 初川 雄一*; 橋本 和幸*; 渡辺 智*; 佐伯 秀也*; 本石 章司*

Journal of the Physical Society of Japan, 89(3), p.034201_1 - 034201_7, 2020/03

 被引用回数:2 パーセンタイル:51.78(Physics, Multidisciplinary)

ポリエチレン遮へい中の$$^{68}$$ZnOに、50MeV重陽子と$$^{9}$$Beによる($$d,n$$)反応で生成した中性子を照射することで、$$^{67}$$Ga, $$^{66}$$Ga, $$^{rm 69m}$$Zn、並びに$$^{64}$$Cuの特異な生成を実験的に確認した。特に、ポリエチレン遮へい内で得られた収率は、遮へいなしの実験と比較して、約20倍の収量を示した。一方、鉛遮へい内の金属$$^{68}$$Zn試料の照射における$$^{67}$$Ga, $$^{66}$$Ga, $$^{rm 69m}$$Zn、並びに$$^{64}$$Cuの収量と、$$^{68}$$ZnO及び金属$$^{68}$$Zn試料の照射における$$^{67}$$Cu, $$^{65}$$Ni及び$$^{65}$$Znの収量は、遮へいによる影響はほとんど受けていない。この実験結果は、遮へい条件を調整することで、中性子反応に限らず陽子反応を含む多様で大量の放射性同位元素を、一度の照射で同時に合成できるという加速器中性子の注目すべき特性を示すものである。また、PHITSコードを利用した生成量予測を試み、本実験結果と比較することで、本生成量の特異性について評価した。


JENDL/ImPACT-2018; A New nuclear data library for innovative studies on transmutation of long-lived fission products

国枝 賢; 古立 直也; 湊 太志; 岩本 信之; 岩本 修; 中山 梓介; 江幡 修一郎*; 吉田 亨*; 西原 健司; 渡辺 幸信*; et al.

Journal of Nuclear Science and Technology, 56(12), p.1073 - 1091, 2019/12

 被引用回数:3 パーセンタイル:57.07(Nuclear Science & Technology)

長寿命核分裂生成核種(LLFP)の核変換技術確立に向けた革新的研究開発に資することを目的とし、新たな核データライブラリJENDL/ImPACT-2018を開発した。開発した核データライブラリは主要なLLFPである$$^{79}$$Se, $$^{93}$$Zr, $$^{107}$$Pd, $$^{135}$$Csおよび周辺核種(計163核種)に対する中性子及び陽子入射の評価済核反応断面積がエネルギー200MeVを上限として格納されている。断面積の評価においては核反応モデルコードCCONEを用いると共に、測定データの乏しい核種やエネルギー領域の断面積を根拠を持って推定するために微視的な核構造理論を積極的に活用した。また、近年RIBF/RIKENにおいて逆運動学を用いて測定された測定データに基づいて主要な核反応モデルパラメータを最適化した。得られたデータは従来手法により求められた既存の核データライブラリJENDL-4.0/HEやTENDL-2017に比べて、安定核種に対する測定データをよく再現することを確認した。


Progress of criticality control study on fuel debris by Japan Atomic Energy Agency to support Secretariat of Nuclear Regulation Authority

外池 幸太郎; 渡邉 友章; 郡司 智; 山根 祐一; 長家 康展; 梅田 幹; 井澤 一彦; 小川 和彦

Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019) (Internet), 9 Pages, 2019/09



Assessment of radiation doses from ingestion pathway to the public in Fukushima prefecture after the Fukushima Dai-ichi Nuclear Power Plant accident

高原 省五; 渡邊 正敏*

Proceedings of Asian Symposium on Risk Assessment and Management 2019 (ASRAM 2019) (USB Flash Drive), 9 Pages, 2019/09



CFD analysis of the CIGMA experiments on the heated JET injection into containment vessel with external surface cooling

Hamdani, A.; 安部 諭; 石垣 将宏; 柴本 泰照; 与能本 泰介

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.5463 - 5479, 2019/08

The present study introduces thermal mixing and stratification produced by heated air jet located at the bottom level of the containment vessel. The investigation was carried out experimentally and numerically in the large containment vessel called CIGMA (Containment InteGral effects Measurement Apparatus). The experiments were conducted with external surface cooling and various air jet inlet temperatures. The containment cooling was done by flooding the water on the external side of half-upper of a vessel. To identify their influence on the thermal mixing and stratification phenomena, the investigation focuses on mixing convection which occurred in the cooled region of a containment vessel. Temperature distribution and jet velocity were measured by thermocouple and Particle Image Velocimetry (PIV) respectively. Numerical simulation was performed using Computational Fluid Dynamics (CFD) code OpenFOAM to investigate the detail effects of external cooling on the fluid flow and thermal characteristics in the test vessel. CFD results showed a good agreement with experimental data on both temperature and velocity. Both temperature and velocity of hot air jet decayed rapidly downstream jet nozzle. Thermal stratification was observed by visualization of temperature contour maps over a cross-section in the containment vessel. Vigorous mixing was also noticed in the upper region of the containment vessel. Effect of external cooling on mixing and the thermal stratification were presented and discussed.

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