Flow regimes and heat transfer for opposing flow mixed convection in the thermal entry region of a vertical tube

茂木 孝介; 柴本 泰照; 日引 俊詞*

International Journal of Heat and Mass Transfer, 252, p.127451_1 - 127451_16, 2025/12

https://doi.org/10.1016/j.ijheatmasstransfer.2025.127451

This study focused on the thermal entry length problem for turbulent opposing flow mixed convection in a vertical tube. A Reynolds-averaged Navier-Stokes (RANS) simulation was performed using the turbulence model, and its results were compared with previous experimental data. The simulation results revealed several flow structures and heat transfer characteristics in the entry region, which varied depending on the competing strength of forced and natural convection. Flow regimes were classified based on their flow structures as follows: (a) Non-separating flow regime: When natural convection minimally influences the flow field, the Nusselt number in the entry region is higher than that in the fully developed region. As the influence of natural convection strengthens, the entry length decreases. (b) Separation bubble regime: As the influence of natural convection on the flow field increases, the velocity boundary layer along the heated wall in the entry region separates, leading to the formation of a recirculation region known as a separation bubble. Here, the depression in the Nusselt number distribution was observed owing to the thickening of the thermal boundary layer caused by the separation bubble. (c) Reverse flow regime: Further strengthening of the influence of natural convection leads to the formation of reverse flow along the entire heated wall. Here, the Nusselt number exhibits a nearly flat distribution in the entry region because the reverse flow thickens the thermal boundary layer. A flow regime map based on the results of the RANS simulation was created and proposed in this paper.

Influence of steam flow rate on oxidation kinetics of silicon carbide at 1400-1600 C

Pham V. H.; 倉田 正輝; 永江 勇二; 石橋 良*; 佐々木 政名*

Corrosion Science, 255, p.113098_1 - 113098_9, 2025/10

https://doi.org/10.1016/j.corsci.2025.113098

Being expected as materials for accident tolerant fuel cladding tube, oxidation behavior and kinetics of silicon carbide (SiC) under extreme conditions like severe accidents must be elucidated. In this study, oxidation tests of SiC at 1400-1600 C for 1-5 h, at atmospheric pressure, under two different flow rates of HO/Ar gas mixture have been conducted to investigate the influence of steam flow rate on the formation of SiO scale and its subsequent volatilization. The oxidation tests were conducted via a newly developed test facility using laser as a heat source. Oxidation kinetics of SiC was evaluated via mass change of samples before and after the oxidation tests. Parabolic oxidation rate representative for SiO formation and linear volatilization rate reflecting its volatilization were calculated, based on these mass changes. The Arrhenius dependence of the parabolic oxidation and linear volatilization rate constants were then plotted. Results of this study indicated that SiC exhibits excellent performance under the conditions investigated. Steam flow rate has a significant influence on volatilization of SiO but has minor effects over its formation. Oxidation of SiC in steam at high temperature may follow mass gain or mass loss regime, depending on the steam flow rate. Two oxidation patterns were suggested and discussed. In the first oxidation pattern, the SiO formation is dominated over its volatilization. The second oxidation pattern (steady stage) is reached when the SiO formation rate is equivalent to its volatilization rate. Time to reach this steady stage was defined, based on the parabolic oxidation rate and linear volatilization rate.

Heat transfer coefficient modeling for downward saturated boiling flows in vertical pipes

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

https://doi.org/10.1016/j.ijheatmasstransfer.2025.127219

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.

Experimental study on light gas transport during containment venting by using the large-scale test facility CIGMA

相馬 秀; 石垣 将宏*; 柴本 泰照

Annals of Nuclear Energy, 219, p.111455_1 - 111455_12, 2025/09

https://doi.org/10.1016/j.anucene.2025.111455

Containment venting is one of the accident mitigation measures during severe accidents in nuclear power plants for preventing overpressure failure of the containment vessels. Because of the capability of releasing hydrogen generated in the containment vessel, the hydrogen risk can be also reduced. In this study, we conducted experiments with the large-scale test facility CIGMA to investigate the light gas transport during the venting action, mainly focusing on the effect of sump water boiling caused by the vent. The CIGMA test vessel initially pressurized by steam, air, and helium (hydrogen simulant) that formed a helium-rich density stratification was depressurized with and without sump water, with different venting flow rates, and at different venting positions. As the sump water became a steam source due to flash boiling, the helium stratification was diluted and the venting time increased twofold compared to the case without sump water, which significantly affected the amount of helium discharged to the atmosphere. Especially for the high venting flow rate condition, the amount of helium remaining in the vessel at the end of depressurization was half that of the case without sump water. Lowering the venting position from within the initial stratification to 3 m below its interface led to a threefold increase in the amount of helium remaining at the same low pressure, because of the longer time until the helium-rich stratification reached the venting position.

Enhanced work hardening in ferrite and austenite of duplex stainless steel at 200 K; neutron diffraction study

山下 享介*; 古賀 紀光*; Mao, W.*; Gong, W.; 川崎 卓郎; Harjo, S.; 藤井 英俊*; 梅澤 修*

Materials Science and Engineering A, 941, p.148602_1 - 148602_11, 2025/09

https://doi.org/10.1016/j.msea.2025.148602

Ferrite-austenite duplex stainless steels offer excellent strength and ductility, making them suitable for extreme environments. In this study, neutron diffraction during tensile testing at 293 K and 200 K was used to investigate stress partitioning and phase-specific deformation. Phase stress was calculated using a texture-compensated method. At both temperatures, ferrite showed higher phase stress than austenite, acting as the harder phase. At 200 K, both phases exhibited increased strength and work hardening. Austenite showed significant stacking fault formation alongside dislocation migration, while ferrite retained its dislocation-based deformation mode, becoming more effective. Stress contributions from both phases were comparable. No martensitic transformation occurred. Strengthening and enhanced work hardening in both phases led to high strength at 200 K, with ductility similar to that at 293 K.

Detection of beta-emitting radioactive hotspots inside the Fukushima Daiichi Nuclear Power Station Unit 3 reactor building using an optical fiber radiation sensor based on wavelength-resolving analysis

寺阪 祐太; 佐藤 優樹; 一場 雄太*

Radiation Measurements, 187, p.107486_1 - 107486_8, 2025/09

https://doi.org/10.1016/j.radmeas.2025.107486

We measured the distribution of beta-ray emitters inside the Fukushima Daiichi Nuclear Power Station Unit 3 reactor building using a novel optical fiber-based position-sensitive radiation sensor designed for operation in high dose rate environments. Plastic scintillation fibers (PSFs) were installed inside the Unit 3 reactor building, where scintillation light generated through interactions between radiation and the PSFs was detected by a spectrometer to obtain the wavelength spectrum. By applying an unfolding method to the wavelength spectrum, we estimated the distribution of beta ray emitters along the PSFs. To isolate the beta ray contribution in a high gamma dose rate field, we compared measurements taken with and without a stainless steel tube serving as a beta ray shield. As a result, we identified a hotspot predominantly influenced by beta rays for the first time in the high dose rate area on the southern side of the first floor of the Unit 3 reactor building.

Modeling the extraction of bound rubber from silica-filled styrene-butadiene rubber with toluene

田村 由起子*; 荒川 勝利*; 竹中 幹人*; 中西 洋平*; 藤波 想*; 柴田 基樹*; 山本 勝宏*; 宮田 登*; 山田 雅子*; 瀬戸 秀紀*; et al.

Polymer, 333, p.128662_1 - 128662_8, 2025/08

https://doi.org/10.1016/j.polymer.2025.128662

To investigate the relationship between the mechanical properties of silica-filled styrene-butadiene rubber (SBR) and the amount of bound rubber at the filler/rubber interface, the polymer matrix was extracted from silica-filled SBR using toluene at room temperature. In this study, this extraction process was reproduced by leaching a thermally annealed SBR layer deposited on a Si substrate in toluene at room temperature, where the adsorption layer of the SBR was grown at the interface with the substrate by thermal annealing. The SBR adsorption layer on the Si substrate has two-layer structures consisting of an inner and outer adsorption layers, which correspond to the tightly and loosely bound rubbers on the filler surface of the silica-filled SBR, respectively. For the sample annealed for less than 6 h, the outer adsorption layer, loosely bound to the substrate, was easily leached in toluene for 5 min, leaving only the inner adsorption layer on the substrate. For the samples annealed for more than 24 h, a large portion of the outer adsorption layer remained on top of the inner adsorption layer as a terrace structure. However, even for the sample annealed for 24 h, treating with toluene for 24 h completely leached the outer adsorption layer from the inner adsorption layer, although the inner adsorption layer remained on the substrate. It was found that the loosely bound rubber in the silica-filled SBR could be easily extracted from the filler surface, along with the free polymer chains in the polymer matrix during extraction with toluene at room temperature. In contrast, the tightly bound rubber was not leached by toluene at room temperature. This may be because the interfacial polymer chains within approximately 1 nm of the substrate surface were strongly constrained to the substrate, and even toluene molecules were excluded.

HTTRを用いた安全性実証試験の完遂; 炉心流量喪失試験(出力100%(30MW)で炉心冷却を停止)

長住 達; 長谷川 俊成; 中川 繁昭; 久保 真治; 飯垣 和彦; 篠原 正憲; 七種 明雄; 野尻 直喜; 齋藤 賢司; 古澤 孝之; et al.

JAEA-Research 2025-005, 23 Pages, 2025/07

JAEA-Research-2025-005.pdf:2.68MB

高温ガス炉の異常状態での安全性を示すため、HTTRを用いて安全性実証試験を行った。制御棒による停止操作の失敗事象を模擬した状態で、原子炉熱出力100%(30MW)での定常運転時に1次ヘリウムガス循環機を急停止させ、炉心の強制循環冷却機能が全喪失した後の原子炉出力および原子炉圧力容器まわり温度の経時変化データを取得した。事象発生(冷却材の流量がゼロ)後、炉心温度上昇に伴う負の反応度フィードバックにより原子炉熱出力は速やかに低下し、再臨界を経て低出力(約1.2%)の安定な状態まで原子炉出力が自発的に移行することを確認した。また、原子炉圧力容器表面から、その周囲に設置されている炉容器冷却設備(水冷パネル)への放熱により、低出力状態で原子炉温度を一定化させるために必要な除熱量が確保されることを確認した。このように、出力100%(30MW)で炉心強制冷却を停止したケースにおいて、能動的停止操作をせずとも原子炉の状態が事象発生から安定的(安全)状態へ移行すること、すなわち高温ガス炉の固有の安全性を実証した。

Integrated thermal power measurement in the modified STACY for the performance inspections

荒木 祥平; 會澤 栄寿; 村上 貴彦; 新垣 優; 多田 裕太; 神川 豊; 長谷川 健太; 吉川 智輝; 住谷 正人; 関 真和; et al.

Annals of Nuclear Energy, 217, p.111323_1 - 111323_8, 2025/07

https://doi.org/10.1016/j.anucene.2025.111323

原子力機構では、臨界集合体STACYを均質溶液体系から非均質軽水減速体系へと更新した。STACY更新炉においても最大熱出力は200Wと定められており、熱出力校正は運転を行う上で重要である。熱出力測定においては、溶液系STACYで用いていたFPの分析による熱出力の評価が適応できなかったため、放射化法をベースとする実験データと数値計算を組み合わせて出力を評価する手法をSTACY更新炉の体系に適応し、測定を実施した。測定データを基に出力校正を実施した結果、校正後の指示値は放射化法による測定結果と3%以内で一致した。

Experimental and modeling studies on the oxygen ingression behavior at the crevices of stainless steels in high-temperature water

相馬 康孝; 小松 篤史; 加治 芳行; 山本 正弘*; 五十嵐 誉廣

Corrosion Science, 251, p.112897_1 - 112897_15, 2025/07

https://doi.org/10.1016/j.corsci.2025.112897

高温水中(288C)におけるステンレス鋼のすき間内部への酸素侵入に関する実験およびモデリング研究を実施した。すき間内への酸素侵入の限界距離は、酸素濃度、すき間幅、浸漬時間に関わらず、すき間開口部からの距離dがそれ以上の数値になる場合、主要表面酸化物組成が(ヘマタイトマグネタイトに)変化する位置として定義することができた。その場測定により、付近での電気伝導度の増加が確認され、これは酸素濃度差電池によるイオン濃縮を示した。は、すき間幅、酸素濃度、浸漬時間の増加に伴って拡大した。モデル計算の結果、酸化膜の成長によってステンレス鋼金属のアノード溶解が抑制され、対応する酸素のカソード還元消費速度が低下することで、時間とともに酸素の侵入が進行することが示唆された。