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Droplet generation during liquid jet impingement onto a horizontal plate

Zhan, Y.*; 大箭 直輝*; 榎木 光治*; 大川 富雄*; 青柳 光裕; 高田 孝

Experimental Thermal and Fluid Science, 98, p.86 - 94, 2018/11


In sodium-cooled fast reactors, liquid sodium leakage may lead to fire accident. In the case that the liquid sodium is discharged as a liquid jet, a number of droplets are produced during liquid jet impingement on the structures. In the present work, a liquid jet was emanated vertically downward from a circular nozzle hole onto a horizontal disk to measure the total amount and the maximum size of splashed droplets. It was found that a significant amount of liquid was splashed when the liquid jet impinged as a broken jet. Thus, a prediction method was first developed for the impact frequency of the primary droplets produced due to the jet breakup. It was then shown that a phenomenological model using the impact frequency and the impact Weber number as the important variables can predict the splashing rate well. It was also indicated that the size of the maximum splashed droplets was fairly proportional to the size of primary droplets.


Cavitation erosion induced by proton beam bombarding mercury target for high-power spallation neutron sources

二川 正敏; 直江 崇; 粉川 広行; 羽賀 勝洋; 沖田 浩平*

Experimental Thermal and Fluid Science, 57, p.365 - 370, 2014/09

 被引用回数:5 パーセンタイル:53(Thermodynamics)



Measurement of non-condensable gas in a PWR small-break LOCA simulation test with LSTF for OECD/NEA ROSA project and RELAP5 post-test analysis

竹田 武司; 大和田 明彦; 中村 秀夫

Experimental Thermal and Fluid Science, 51, p.112 - 121, 2013/11

 被引用回数:9 パーセンタイル:40.91(Thermodynamics)

An OECD/NEA ROSA Project experiment was conducted simulating a PWR 0.5% cold leg small-break LOCA with steam generator (SG) secondary-side depressurization as an accident management measure to clarify such complex phenomena as non-uniform flow among the SG U-tubes under natural circulation (NC) with air as non-condensable gas. The gas concentration was measured at the SG outlet plenum by using a gas measurement device to measure oxygen concentration in steam-gas mixture that is developed employing a Zirconia sensor. Non-uniform flow behaviors were observed in the SG U-tubes with non-condensable gas ingress. Air concentration in steam-gas mixture was estimated to be about 40-50% at the SG outlet plena after the U-tube downflow side became empty of liquid. Post-test analysis by RELAP5/MOD3.2.1.2 code revealed that the code underpredicts the primary pressure a bit after the gas inflow with some discrepancies in the SG U-tube liquid level and the NC mass flow rate.


An Experimental investigation on self-leveling behavior of debris beds using gas-injection

Cheng, S.; 山野 秀将; 鈴木 徹; 飛田 吉春; 権代 陽嗣*; 中村 裕也*; Zhang, B.*; 松元 達也*; 守田 幸路*

Experimental Thermal and Fluid Science, 48, p.110 - 121, 2013/07

 被引用回数:13 パーセンタイル:29.21(Thermodynamics)

Although in the past, several experiments have been conducted to investigate the self-leveling behavior of debris beds, most of these were under comparatively lower gas velocities, the findings of which might be not directly applicable to actual reactor accident conditions. Current experiments were conducted using gas-injection in a large-scale cylindrical tank, in which nitrogen gas, water and different kinds of solid particles, simulate the fission gas, coolant and fuel debris, respectively. During experiments, to accomplish the bubble-based leveling as expected in reactor conditions, two experimental approaches, termed respectively as the gas pre-charge method and the pressure-adjustment method, have been attempted. Through elaborate comparisons and evaluations, it is found that compared to the gas pre-charge way the pressure-adjustment method can alleviate the liquid disturbance from bottom inlet pipelines more effectively. Further, based on experimental data using pressure-adjustment method, influence of particle size, particle density and gas flow rate on the leveling has been confirmed under current higher gas velocities. In addition, the liquid convection in the water pool, which is not evident within lower gas velocities, is observed to play an important role within current conditions, especially for experimental runs using larger-size but lower-density particles at rather higher gas flow rates.


Optically observation of mercury cavitation bubble collapsing

直江 崇; 二川 正敏

Experimental Thermal and Fluid Science, 44, p.550 - 555, 2013/01

 被引用回数:2 パーセンタイル:78.45(Thermodynamics)



Dynamic responses of a solid wall in contact with a bubbly liquid excited by thermal shock loading

二川 正敏; 直江 崇

Experimental Thermal and Fluid Science, 35(6), p.1177 - 1183, 2011/09

 被引用回数:3 パーセンタイル:68.23(Thermodynamics)



Experimental investigation of bubbling in particle beds with high solid holdup

Cheng, S.*; 平原 大輔*; 田中 鷹平*; 権代 陽嗣*; Zhang, B.*; 松元 達也*; 守田 幸路*; 福田 研二*; 山野 秀将; 鈴木 徹; et al.

Experimental Thermal and Fluid Science, 35(2), p.405 - 415, 2011/02

 被引用回数:19 パーセンタイル:21.28(Thermodynamics)

水を液体として用い観察タンクの底から窒素を発生させバブルを作る実験が2次元(2D)3次元(3D)それぞれの状態で個別に行われた。粒子ベッド高さ(30mmから200mm),粒子直径(0.4mmから6mm)そして、粒子タイプ(アクリルビーズ,ガラス,アルミ,ジルコニウム)等で粒子ベッドに変化を持たせた。これらの実験でイメージ解析によって初めて3種類のバブル特性が観察され、さらに表面バブル頻度、2D, 3D状態の表面バブルサイズなどのバブル挙動の定量的な詳細分析で検証された。


Experimental results of heat transfer coefficients and friction factors in a 2D/3D rib-roughened annulus

高瀬 和之

Experimental Thermal and Fluid Science, 13(2), p.142 - 151, 1996/08

 被引用回数:7 パーセンタイル:49.21



Thermal-hydraulic study on a double-flat-core high conversion light water reactor

杉本 純; 岩村 公道; 大久保 努; 村尾 良夫

Experimental Thermal and Fluid Science, 4, p.354 - 361, 1991/00




Evaluation of heat conduction and visualization of heat flux in a plate making use of heat transfer experiments

功刀 資彰; 秋野 詔夫; 一宮 浩市*; 高木 一郎*

Experimental Thermal and Fluid Science, 4, p.448 - 451, 1991/00

 被引用回数:3 パーセンタイル:63.67



Results of 0.5% cold-leg small-break LOCA experiments at ROSA-IV/LSTF; Effect of break orientation

浅香 英明; 久木田 豊; 与能本 泰介; 小泉 安郎; 田坂 完二

Experimental Thermal and Fluid Science, 3, p.588 - 596, 1990/00

 被引用回数:18 パーセンタイル:20.43


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