Experimental investigations of the flow patterns in the hot leg of a pressurized water reactor (original) (raw)

Computational Fluid Dynamics Applied to Study Coolant Loss Regimes in Very High Temperature Reactors

Uebert Moreira

Brazilian Journal of Radiation Sciences

View PDFchevron_right

Characterization and prediction of flow-conditions in the hot-leg of PWR during loss of coolant accident

kumar samal

Nuclear Engineering and Design, 2020

View PDFchevron_right

CFD analysis of coolant flow at bushehr nuclear reactor

babak khanbabaei

View PDFchevron_right

Preliminary numerical analysis of the flow distribution in the core of a research reactor

Pedro Umbehaun

2020

View PDFchevron_right

Fluid-Structure Interaction for Coolant Flow in Research-type Nuclear Reactors

Franklin Curtis, Kivanc Ekici

View PDFchevron_right

CFD model of fluid flow in reactor : A simulation of velocity and heat distribution in a channel

Erik Arlemark

2006

View PDFchevron_right

Two-Phase Flow Heat Transfer in Nuclear Reactor Systems

Yassin Hassan

Science and Technology of Nuclear Installations, 2013

View PDFchevron_right

Thermal-Hydraulics in Nuclear Reactors

MOCHIZUKI Hiroyasu

2009

View PDFchevron_right

CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core

Salah El-Din El-Morshedy

Annals of Nuclear Energy, 2012

View PDFchevron_right

Thermal-Hydraulic Analysis of Partial Loss of Forced Reactor Coolant Flow with Non-Uniform and Asymmetric Loop Flow Mixing in VVER-1000

krishnakumar P

7th International and 45th National Conference on Fluid Mechanics and Fluid Power (FMFP), 2018

View PDFchevron_right

Numerical Simulation Study on the Air/Water Counter- current Flow Limitation in Nuclear Reactors

Youssef Morghi

Brazilian Journal of Radiation Sciences

View PDFchevron_right

Thermal-Hydraulic Analysis of Nuclear Reactors

Mostafijur RAHMAN Kazi

2015

View PDFchevron_right

Design method of flow distribution in nuclear reactor systems

Junye Wang

Chemical Engineering Research and Design, 2013

View PDFchevron_right

Interfacial behavior of the air-water counter-current two-phase flow in a 1/30 scale-down of pressurized water reactor (PWR) hot leg

Okto Dinaryanto

Annals of Nuclear Energy, 2018

View PDFchevron_right

3D modeling of the primary circuit in the reactor pressure vessel of a PHWR

Norberto Nigro

Nuclear Engineering and Design, 2013

View PDFchevron_right

CFD-Calculation of Fluid Flow in a Pressurized Water Reactor

babak khanbabaei

Journal of Sciences, Islamic …, 2008

View PDFchevron_right

Unsteady Elbow Pipe Flow to Develop a Flow-Induced Vibration Evaluation Methodology for Japan Sodium-Cooled Fast Reactor

yukiharu iwamoto

Journal of Nuclear Science and Technology, 2011

View PDFchevron_right

Study of the Natural Circulation Phenomenon for Nuclear Reactors

Pedro Umbehaun

2011

View PDFchevron_right

Loss of Flow Accident Analyses in Tehran Research Reactor

ahmad lashkari

2016

View PDFchevron_right

Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools

Victor Sanchez, Victor Hugo Sanchez Espinoza

Science and Technology of Nuclear Installations, 2010

View PDFchevron_right

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

Minhajur Rahman

Experimental and Computational Multiphase Flow

View PDFchevron_right

A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions

Anamika dixit

Nuclear Engineering and Design, 2010

View PDFchevron_right

Numerical Simulation of Axial Coolant Flow in Rod Bundles of a Nuclear Reactor

Y. Rihan

The 7th International Conference on Information Technology, 2015

View PDFchevron_right

Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling

Ikuo Kinoshita

Journal of Nuclear Science and Technology, 2010

View PDFchevron_right

Flow instabilities in boiling channels of pressure-tube-type reactor

弘保 望月

Nuclear Engineering and Design, 1994

View PDFchevron_right

Measurements Methods for the analysis of Nuclear Reactors Thermal Hydraulic in Water Scaled Facilities

Philippe Planquart

EPJ Web of Conferences, 2018

View PDFchevron_right

Coolant mixing in pressurized water reactors

Ulrich Rohde

View PDFchevron_right

The Use of CFD Code for Numerical Simulation Study on the Air/Water Countercurrent Flow Limitation in Nuclear Reactors

Youssef Morghi

2015

View PDFchevron_right

Data Collection Methods for Validation of Advanced Multi-Resolution Fast Reactor Simulations

arthur ruggles

2015

View PDFchevron_right

Fluid-structure interactions in light water reactor systems

U. Schumann

Nuclear Engineering and Design, 1980

View PDFchevron_right

Reactor Hydrodynamics during the Reflood Phase of a Loss-of-Coolant Accident

Rodney Gay

Nuclear Technology, 1977

View PDFchevron_right

Simulation of Flow Distribution in Radial Flow Reactors

H. al-Ali, H. Zughbi

Industrial & Engineering Chemistry Research, 2006

View PDFchevron_right