TIETHYS
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Facility name:
Facility type:
IET - Integral Effects Test facility
SET - Separate Effects Test facility
CFD - Computational Fluid Dynamics facility
Country:
Canada
Czech Republic
Finland
France
Germany
Hungary
Italy
Japan
Korea
Netherlands
Norway
Russian Federation
Sweden
Switzerland
United Kingdom
United States of America
Organization:
ABB Reactor GmbH
Atomic Energy of Canada Limited
AERE Harwell
Argonne National Laboratory
Ansaldo Nucleare
AREVA NP
Babcock & Wilcox
BMFT-KWU
Battelle-Institute
State Univ. New York at Buffalo
University of Kentucky Center for Applied Energy Research
Constellation Energy
Commissariat à l'énergie atomique
Central Electricity Generating Board (CEGB) - Marchwood Engineering Laboratory (MEL)
Centro Informazioni, Studi ed Esperienze
Centro Informazioni, Studi ed Esperienze-SIET
CREARE
Chalk River Laboratories
Columbia University
Dartmouth college, Wallis
Energy research Centre of the Netherlands
EDO Gidropress
ENEA
Electrogorsk Research and Engineering Center
ESTMTF/SAI
Forschungszentrum Rossendorf (FZR)
General Electric
Halden Reactor
Hitachi
University of Houston
Idaho National Engineering Laboratory (INEL)
Idaho National Laboratory
Institute of Physics and Power Engineering
Imatran Voima Oy
Japan Atomic Energy Research Institute
Joint Research Center of the Commission of the European Communities , Ispra
Korea Atomic Energy Research Institute
Kernenergieausstiegs (KFK)
Hungarian Academy of Sciences KFKI Atomic Energy Research Institute
KTH Royal Institute of Technology
Kraftwerk Union AG (KWU)
Kernforschungszentrum Karlsruhe - IATF
Lappeenranta University of Technology (LUT)
Lehigh University
Massachusetts Institute of Technology
Moscow Power Engineering Institute
Marviken Power Station
A.P.Aleksandrov Scientific Research Technological Institute
UK National Nuclear Corporation
NPP NV-AEP
UK-Leatherhead-National Power Technology & Environmental Centre
NUPEC
Northwestern University, Illinois
Oak Ridge National Laboratory
Oregon State University
PSI-Villigen
Pennsylvania State University
TURIN POLYTECHNIC
Purdue University
State Atomic Energy Corporation
Russian Research Center Kurchatov Institute
SIET S.p.A.
Seoul National University
Standford Research Institute
State University of New York at Buffalo
Skoda
Stern Laboratories Inc.
University of Strathclyde
Studsvik Energiteknik AB
TH Zittau
Delft University of Technology
Toshiba
University of California, Berkeley
University of California, Los Angeles
University of California, Santa Barbara
UK-MARCHWOOD
UKAEA
UKAEA-Harwell
UKAEA-Winfrith
University of Maryland College Park
University of Stuttgart
University of Pisa
Unknown
VTT Energy
Vattenfall
Westinghouse
Whiteshell Laboratories
Operating year:
1960
1961
1962
1963
1964
1965
1966
1967
1968
1969
1970
1971
1972
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1974
1975
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2007
2008
2009
2010
2011
2012
2013
2014
2015
2016
2017
2018
2019
2020
2021
2022
2023
2024
2025
≤ y ≤
1960
1961
1962
1963
1964
1965
1966
1967
1968
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
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2008
2009
2010
2011
2012
2013
2014
2015
2016
2017
2018
2019
2020
2021
2022
2023
2024
2025
Reference reactor:
Time scale:
≤ t ≤
Volumetric scale:
⅟
≤ v ≤
⅟
Height scale:
≤ h ≤
Core heating method:
Direct
Indirect
Indirect(BWR)
Nuclear
Skin
Nb. simulated rods:
≤ n ≤
Scenario:
Accident management for a non degraded core
Ageing
Fuel handling accidents
Large Break LOCA
Loss of flow
Loss of regulation
Moderator and shield system failures
Small/Medium Break LOCA
Secondary side failures
Single channel events
Steady-State
Transients at shutdown conditions
Transients
Applies to IET and CFD facilities only.
Phenomenon:
Pump performance for 1-2 phases
2-phase pressure drop
Accumulator behaviour
Asymmetric loop behaviour
Boron mixing and transport
Break Flow
Bypass Axial Flow and Void Distribution
Channel Axial Flow and Void Distribution
Collapsed Level Behaviour in Downcomer (BWR)
Condensation
Core wide void distribution
Corewide Radial Void Distribution
Counter Current Flow Limitation (CCFL)
Departure from Nucleate Boiling (DNB)
Dryer Behavior
ECC Bypass
Entrainment and Deentainment
Flashing
Global Multidimensional Fluid Temperature, Void and Flow Distribution
Heat Transfer : Core
Heat Transfer : SG
Instability
Isokinetic Turbulent Mixing
Jet Pump Behavior
Loop Seal Phenomena (CL)
Loop Seal Phenomena (HL)
Mixture level
Natural Circulation
Noncondensable gas effects
Nuclear Thermalhydraulic feedback
Parallel Channel LOCA
Parallel Channel instabilities
Phase separation
Pressurization due to boiling
Pressurizer Behavior
Quench Phenomena
Spray Cooling in Upper Head
Steam Binding
Steam Line Dynamics
Steam Separator Behavior
Steam Splurging
Stored energy (fuel)
Stratification in horizontal pipes
Stratified Flow
Stratified Hydrogen Concentrations with Jets
Structural heat and heat losses
Thermal Fatigue
Thermalhydraulics : BWR Core
Thermalhydraulics : PWR Core
Thermalhydraulics : SG
Three dimensional flow (core)
T_min/ Rewet temperature
Turbulent Flow
UP to Downcomer Leak Flow
Void Collapse and Temp, Distribution During Pressurization
Void Distribution
Wake Flow
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