441 results on '"Ninokata, Hisashi"'
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202. DEVELOPMENT OF AN LES METHODOLOGY FOR COMPLEX GEOMETRIES
203. Numerical Studies on Dynamic Behavior of Air-Water Cross Flow Between Two Circular Interconnected Channels
204. Numerical Simulation of Free-Surface Vortices
205. Priori Test of the Flow in an Annular Channel With Differential Heating at the Walls
206. Unsteady Reynolds-averaged Navier-Stokes: toward accurate prediction of turbulent mixing phenomena
207. Simulation of Eccentric-Shaft Journal Microbearing by DSMC
208. Cylindrical Couette Flow of a Rarefied Gas From Macro- to Micro-Scales
209. Large Eddy Simulation of the Flow in Tight-Lattice Rod Bundles at Low Reynolds Number
210. Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I)
211. Biglobal linear stability analysis for the flow in eccentric annular channels and a related geometry
212. Anisotropic Turbulence and Coherent Structures in Eccentric Annular Channels
213. Evaluation Method for Flow Accelerated Corrosion of Components by Corrosion Analysis Coupled with Flow Dynamics Analysis
214. Key Issues in R&Ds and Their Prospective views Related to LMFBR Core Disruptive Accidents
215. Thermohydraulics Analysis of local Subassembly Accidents in Liquid Metal Cooled Fast Breeder Reactors
216. Subchannel Analysis in Nuclear Reactors
217. PRA-Based SMA: the First Tool toward a Risk-Informed Approach to the Seismic Design of the IRIS
218. Improved Turbulence Modeling for Performance Evaluation of Novel Fuel Designs
219. Advanced Scientific Computational Methods and Their Applications to Nuclear Technologies― (10) Visualization, Present State of Technology and Future Challenge
220. Fast Breeder Reactor : the Past, the Present and the Future―（４）History of Fast Reactor Development in U.S.A-Ⅱ
221. Fast Breeder Reactor : the Past, the Present and the Future―（３）History of Fast Reactor Development U.S.A-Ⅰ
222. Experimental and Numerical Study of Liquid Metal Boiling in a System of Parallel Bundles under Natural Circulation Conditions
223. The pumping performances of the turbomolecular pump simulated by Direct Simulation Monte Carlo method [Progress in Nuclear Energy 47 (2005) 664–671]
224. 2637 Local laminarization of low Re turbulent flows in an FBR fuel subassembly
225. A Three-Dimensional DSMC Simulation of Single-Stage Turbomolecular Pump Adopting Accurate Intermolecular Collisions Models
226. Modelisation d’écoulement diphasique dans l’analyse du sous-canal de grappe d’assemblages
227. 2509 Multi-dimensional Analysis of Two-phase flow inside Subchannel using Extended Two-fluid Model
228. A Modified Equilibrium Void Distribution Model Based on Two-Dimensional Flow Network Applicable for Conventional Fuel Bundles
229. Analysis of droplets behavior around B WR spacer with TF-MPS Method
230. Numerical Simulation of Sodium Pool Fire
231. Calculation of Heat Transfer Coefficients on a Flat Plate by Pseudo Direct Numerical Simulation of Turbulence
232. Numerical Prediction of Secondary Flows in Complex Areas Using Concept of Local Turbulent Reynolds Number
233. Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE
234. Controversial Technical Issues on Nuclear Safety of Prototype FBR Monju Contained in the Decision by the High Court
235. Calculation of Detailed Velocity and Temperature Distributions in a High-Burnup Fuel Subassembly using Pseudo Direct Numerical Simulation
236. Selection of an Appropriate Turbulence Model to Evaluate Performances of Novel Fuel Geometries for the “IRIS” Reactor
237. Direct Numerical Simulation of Turbulent Flows in a Subchannel of Tight Lattice Fuel Pin Bundles of Nuclear Reactors
238. Analytical Study on Detailed Void Distributions Inside BWR Fuel Bundle under Turbine Trip Event Considering Time-Dependent Pin Power Distributions
239. MULTI-SCALE VISCOSITY (MSV) MODEL OF TURBULENCE
240. Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors
241. Numerical Study on Observed Decay Ratio of Coupled Neutronic-Thermal Hydraulic Instability in Ringhals Unit 1 under Random Noise Excitation
242. An Approach of Uncertainty Evaluation for Thermal-Hydraulic Analysis
243. Numerical Prediction of Secondary Flows in Complex Areas Using Concept of Local Turbulent Reynolds Number
244. Preliminary Probabilistic Safety Assessment of the IRIS Plant
245. 平衡ボイド分布モデル改良の方向性 (L-49)
246. TF-MPSによるスペーサー周りの液滴挙動の解析 (L-51)
247. IRISプラントPSAにおける炉心損傷頻度評価 (M-46)
248. サブチャンネル間気泡移動に対する物性因子の影響 (L-48)
249. 二相流複雑流動解析技術による厚肉多孔板のCCFL実験解析 (L31)
250. BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE—II: Application to Ringhals Unit-1 Stability Test
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