Analysis and Implementation of Design Extension Conditions at Czech NPPs and Contribution (DEC) at Czech NPP5 and Contribution of DEC to Enhancement of Defence-in-Depth

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9
1. Verfasser: Kral, P. (VerfasserIn)
Pages:18
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
Towards Best Practice Guidelines for Euler-Euler Simulations of Poly-Disperse Bubbly Flows 2020 Lucas, D.
Simulation of the Fukushima Daiichi Unit 2 Severe Accident with MELCOR 2.1 2020 Morreale, A. C.
Observation of Air Bubble Characteristics by a Vertical Nozzle Under Pool Scrubbing Conditions 2020 Yoon, Jongwoong
PIV Measurements Inside a Wire-Wrapped Hexagonal Rod Bundle: From Experiments to Governing Equations 2020 Bertocchi, F.
Thermal-Hydraulic Modeling of Supersonic Steam Injector as a Passive Safety System 2020 Miwa, Shuichiro
Temperature Distribution Measurement During Quenching of High-Temperature Wall with a Falling Liquid Film 2020 Okawa, Tomio
Uncertainty in Calculations by KWU-MIX of Condensation in the Cold Leg and Downcomer During Pressurized Thermal Shock 2020 Trewin, Richard R.
Validation of a BEPU Methodology Through A Blind Benchmark Activity at the PKL Test Facility 2020 Freixa, J.
VIKTORIA Experiments Investigating the Filtering System in the Sump of a PWR After a Loss of Coolant Accident - Part I : Physical/Chemical Effects on Strainer Head Loss Evolution 2020 Repetto, G.
BWR Fuel Bundle Lift Force Measurements, Modeling and Validation 2020 Waldemarsson, F.
Analysis for the Accident at Unit 3 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project 2020 Ishikawa, Jun
Towards a Two-Phase Flow All-Regime Model for Simulating Transitions from Dispersed to Stratified Regimes 2020 Kuidjo, E. V. Kuidjo
Thermal Hydraulic CFD Validation for Liquid Metal Cooled 19-Pin Hexagonal Wire Wrapped Rod Bundle 2020 Batta, A.
Thermal Stratification Analysis in a Pool-Type Geometry 2020 Schneider, James
Experimental Investigation on CHF of Water Flowing in Upward Tube from Subcooled to High Qualities 2020 Yang, Bing
Analysis for the Accident at Unit 2 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project 2020 Tamaki, Hitoshi
Particle Decontamination in a Single Bubble During Pool Scrubbing 2020 Fujiwara, K.
A Collaborative Effort Towards the Accurate Prediction of Turbulent Flow and Heat Transfer in Low-Prandtl Number Fluids 2020 Shams, A.
Liquid Metal Thermal Hydraulics - Outcomes of the SESAME Project 2020 Roelofs, F.
Experimental Investigation of Subcooled Flow Boiling and CHF at High Pressure Using High-Resolution Diagnostics 2020 Kossolapov, A.
Alle Artikel auflisten