ICONE2020-16139 Implementation of a Particle Resuspension Model in a CFD Code: Application to an Air Ingress Scenario in a Vacuum Toroidal Vessel

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:ASME International Conference on Nuclear Engineering (2020 : Online) Proceedings of the ASME International Conference on Nuclear Engineering - 2020 ; Volume 1: Beyond design basis, codes and standards, computational fluid dynamics (CFD), decontamination and decommissioning, nuclear fuel and engineering, nuclear plant engineering
1. Verfasser: Gelain, Thomas (VerfasserIn)
Weitere Verfasser: Ricciardi, Laurent (VerfasserIn), Gensdarmes, Francois (VerfasserIn)
Pages:2020
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
ICONE2020-16484 Experimental Study on Flow Patterns and Pressure Drop of Decaying Swirling Gas- Liquid Flow in a Vertical Pipe 2020 Zhang, Jiarong
ICONE2020-16599 Analysis of Water Retention in Isothermal Vacuum Drying Test 2020 Salazar, Alex III
ICONE2020-16913 In-Vessel Core Melt Retention Strategy Applied for the Rivne VVER-440 Unit 2020 Dubyk, Yaroslav
ICONE2020-16735 Proposal of Inspection Rationalization Method and Application for Sodium Cooled Fast Reactor 2020 Hiroki, Yada
ICONE2020-16753 Heat Transfer for Supercritical Flow With TRACE 2020 Spore, Jay
ICONE2020-16047 Static Application of Transient Hydrodynamic Loads on Vessel Internal Structures As a Result of Pulse Jet Mixer Overblow: High-Frequency Load Acoustic Event 2020 Fant, Brian
ICONE2020-16340 CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill 2020 Peng, Sifan
ICONE2020-16316 Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film 2020 Al-Yahia, Omar S.
ICONE2020-16016 Scenario Development for Nuclear Emergency Decision Deduction Training Platform for Radiographers in Developing Countries: Case Study, Ghana 2020 Oforiwaa, Priscilla Obeng
ICONE2020-16181 Aerosol Source Terms Characterization During Cutting of Fuel Debris Simulants With Different Tools in the Context of Fukushima Daiichi Decommissioning 2020 Porcheron, Emmanuel
ICONE2020-16423 Measurement of Thermal Decomposition Temperature and Rate of Sodium Hydride 2020 Kawaguchi, Munemichi
ICONE2020-16698 Determination of Gross Alpha and Gross Beta Activity Concentration in Bahe River Water Samples Within Xi'an Chanba Area 2020 Qingxu, Yao
ICONE2020-16826 Sensitivity Analysis of External Exposure Dose for Future Burial Measures of Decontamination Soil Generated Outside Fukushima Prefecture 2020 Shimada, Asako
ICONE2020-16082 Finite Element Model to Simulate the Spacer Grid Buckling Characteristics 2020 Yoo, Youngik
ICONE2020-16157 Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants 2020 Hao, Yuchen
ICONE2020-16793 Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions 2020 Yin, Chunyu
ICONE2020-16002 Life Prediction Model for Nuclear Power Plant Intake Structure Exposed to Chloride Environment Based on Similarity Principle 2020 Chen, Sen
ICONE2020-16138 Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network 2020 Sun, Pengpeng
ICONE2020-16198 Design Applicability of the Advanced Spectrum Method Assisted by Time History Analysis for Multiply Supported Piping System 2020 Yoshida, Ayaka
ICONE2020-16235 Classification Analysis of Communication System of Nuclear Power Plant 2020 Yun, Yu
Alle Artikel auflisten