Simulation of Accelerated Deflagrations Using the PPREMICS Software
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2018 |
Gastaldo, Laura |
Assessment of Smoothed Particle Hydrodynamics in Application of High-Wind Risk Analysis
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2018 |
Montanari, Linyu Lin. Nam T. Dinh. Niels |
Verification of Station Blackout Performed in ATLAS Test Facility Using RELAPS/SCDAP and Study The Effect of Posrv Stuck Open in The Station Blackout
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2018 |
Ghani, Ahmed Abdul |
Assessing Operator Performance in Human-Computer Interface Designs for Nuclear Power Plants Using Speed and Accuracy, Subjective Ratings and Eye Movement
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2018 |
Yan, Sheng Yuan |
Influence Study Of Actuation Conditions of Passive Safety System on SGTR
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2018 |
Yang, Zijiang |
Interplay between Liquid-Liquid Secondary Fragmentation and Solidification
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2018 |
Hadj-Achour, Miloud |
Steam Generator Tube Rupture Accident Using Best-Estimate Thermal-Hydraulic Computer Code to Predict Radiological Releases
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2018 |
Douxchamps, Pierre-Alexis |
Assessment of RELAPS-3D Code Capabilities in Modeling Fluid Mixing and Multidimensional Flow Using Data From the Vattenfall 1/5th Scale PWR Test Facility
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2018 |
Frepoli, Michael G. Mankosa. Cesare |
Stability Analysis of Natural Circulation with Salt Freezing: Application to FHR DRACS
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2018 |
Dbai, Mohamed Abou |
CED Simulation of Single- and Two-Phase Natural Convection in the Context of External Reactor Vessel Cooling
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2018 |
Colombo, Marco |
Large Eddy Simulation of a Flow Inside a Helical Coil Steam Generator Test Section for a Small Modular Reactor
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2018 |
Lee, Samuel Jongoh |
Comparison of the Alternative CFD Software OpenFOAM with ANSYS CFX Used for Reactor Containment Applications Based on the Simulation of Light Gas Distributions
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2018 |
Stewering, Joern |
Development of a Modified, Hybrid Nodal-Integral/Finite-Element Method for the Steady-State Convection-Diffusion Equation
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2018 |
Wang, Pengfei |
Test Facility Design for the Measurement and Modelling of Candu Reactor Moderator Flow and Temperature Distributions
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2018 |
Strack, James |
Preliminary Study of An Intelligent Autonomous Operation System for Nuclear Power Plant with Thermal-Hydraulic Analysis Code
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2018 |
Kim, Min-Gil |
Effects of Surface Tension on Two-Phase Annular Flow Across Grid Spacer with Mixing Vanes in a Vertical Pipe
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2018 |
Kawahara, Akimaro |
Study on Simulation of a Facility for CAP1400
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2018 |
Cao, Yine |
Numerical Study of Flow Induced Vibrations in a Wire Wrapped Fuel Assembly
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2018 |
Santis, Dante De |
Measurement of the Apparent Contact Angle of Water on Reactor Materials at Elevated Pressures and Temperatures
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2018 |
Kossolapov, IU BA Artyom |
Effects of Heater Surface Characteristics on Bubble Sliding Induced Heat Transfers During Upward Subcooled Nucleate Boiling
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2018 |
Sarker, Debasish |