MELCOR and ASTEC Validation on Prelude Test

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9
1. Verfasser: Duspiva, J. (VerfasserIn)
Weitere Verfasser: Kotouc, M. (VerfasserIn)
Pages:18
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
Kairos Power Thermal Hydraulics Research and Development 2020 Blandford, Edward
Non-Intrusive Two-Phase Flow Regime Identification Method Using FIV and Machine Learning 2020 Miwa, Shuichiro
Pre-Test Analysis for HYMERES-2 PANDA Tests Series for Steam Injection into Pool Through Spargers 2020 Wang, Xicheng
Quantification of Uncertaintv in Pressure Loss Associated with Manufacturing Tolerances in Nuclear Fuel Assemblies 2020 Vogel, Klaus
Development of the CATHARE 3 Three-Field Model for Simulations in Large Diameter Horizontal Pipes 2020 Fillion, Philippe
Model and Boundary Uncertainty Analysis of PWR LBLOCA Transient Event in RELAPS/MOD3.3 Code 2020 Chiang, Chih-Chia
Improvement of GAMMA+ for Turbulent Mixed Convection of Air in a Vertical Duct of Reactor Cavity Cooling System 2020 Shin, Dong-Ho
CFD Assessment of LOFA Intra Core Natural Circulation in the High Temperature Test Facility 2020 Gutowska, Izabela
Mapping Emergency Cooling Water Spray System Test Results to the AP1000® PWR Spent Fuel Pool Physical Layout 2020 Pinkston, Robert N.
Assessment of Empirical Models and Uncertainty and Sensitivity Study of a High-Velocity Steam Condensation Experiment with TRACE 2020 Jaeger, W.
Condensation Heat Transfer of the Steam-Air Mixture on Bundle Heat Exchanger of PCCS (Passive Containment Cooling System) 2020 Bae, Byoung-Uhn
Overview of Kairos Power Systems Code KP-SAM Development 2020 Zhao, Haihua
A Mechanistic Spray Model for Lumped Parameter Reactor Containment Modeling 2020 Bestion, D.
Improvement of Physical Modeling for Coupled Heat and Mass Transfer in a Cavity with Condensation in the Presence of Non-Condensable Gas 2020 Jiang, Nan
Multi-Scale and Multi-Physics Nuclear Reactor Simulation for the Next Generation LWR Safety Analysis 2020 Yoon, Han Young
A Data-Driven Approach to Scale Bridging in System Simulation 2020 Bao, Han
Investigation of Scaling Distortions for NRELAPS Model of NIST Facility Realized Using the Dynamical Systems Scaling Methodology 2020 Heagy, Stephen A.
Experimental Characterization of Boiling Two-Phase Flow Structures Under BWR Core Operating Conditions 2020 Corre, J.-M. Le
Comparison of Random and Deterministic Sampling Methods for Quantification of the Input Uncertainty in CFD 2020 Rakhimov, A. Cutrono
Performance Analysis of External Drywell Cooling on BWR Mark Il Drywell Head During a Short-Term Station Blackout Scenario by MELCOR 2020 Gui, Miao
Alle Artikel auflisten