Facilities


13 results recovered
Type of Facility: Source Term
CODEX
Organization:
MTA-EK
Type:
Source Term
Description:

Complex measurements were performed at the integral high temperature test facility CODEX (COre Degradation Experiment) between 1995-2002 with electrically heated UO2 fuel rod bundles. The test matrix included the first VVER-440 type integral severe accident experiment.
Type of Facility: Corium
DEFOR
Organization:
KTH
Type:
Corium
Description:

Reactor cavity flooding is a cornerstone of severe accident management strategy in Swedish type BWRs.
Type of Facility: Thermal Hydraulics
E110DBAEKI
Organization:
MTA-EK
Type:
Thermal Hydraulics
Description:

Since the beginning of the 1990s’, several experimental series have been performed at the Hungarian Academy of Sciences KFKI Atomic Energy Research Institute (AEKI) with E110 and Zircaloy claddings.
Type of Facility: Corium
FOREVER
Organization:
KTH
Type:
Corium
Description:

FOREVER program at KTH was concerned with the vessel integrity under the molten corium attack in the reactor lower plenum during a severe accident.
Type of Facility: Thermal Hydraulics
HIPE
Organization:
LUT
Type:
Thermal Hydraulics
Description:

Test facility was designed in such a way that it enables to conduct experiments at any inclination of the flow channel. Test facility will be also used for demonstrational and educational purposes.
Type of Facility: Thermal Hydraulics
PACTEL
Organization:
LUT
Type:
Thermal Hydraulics
Description:

PACTEL is a volumetrically scaled (1: 305) facility including a pressurizer, high and low pressure emergency core cooling systems, and accumulators. The reactor vessel is simulated with a U-tube construction including separate downcomer and core sections.
Type of Facility: Thermal Hydraulics
PAKS
Organization:
MTA-EK
Type:
Thermal Hydraulics
Description:

The activities covered the following three areas:
Type of Facility: Thermal Hydraulics
PCCS
Organization:
LUT
Type:
Thermal Hydraulics
Description:

To study the behavior of the PCCS configuration planned to be used in the ABWR II concept and to gain experimental data for the validation work of MELCOR severe accident code, a scaled down PCCS model was designed and constructed at Lappeenranta University of Technology in Finland in 2012–2013.
Type of Facility: Thermal Hydraulics
PPOOLEX
Organization:
LUT
Type:
Thermal Hydraulics
Description:

The PPOOLEX facility consists of a pressure vessel containing a wet well compartment (condensation pool), dry well compartment, inlet plenum and air/steam line piping.
Type of Facility: Thermal Hydraulics
PWR PACTEL
Organization:
LUT
Type:
Thermal Hydraulics
Description:

The PWR PACTEL facility consists of a reactor pressure vessel model, two loops with vertical steam generators, a pressurizer, and emergency core cooling systems. The new loops and steam generators of EPR style construction enable the PWR and EPR related experimental research.
Type of Facility: Thermal Hydraulics
RUSET
Organization:
MTA-EK
Type:
Thermal Hydraulics
Description:

The RUSET experimental programme was launched in 2002 at the Hungarian Academy of Sciences KFKI Atomic Energy Research Institute (AEKI). The aim of the program was to get data for assessment of ruthenium release at severe accident with air ingress.
Type of Facility: Thermal Hydraulics
SFRD
Organization:
MTA-EK
Type:
Thermal Hydraulics
Description:

The high temperature interaction of reactor core materials during a severe accident leads to the oxidation and melting of metal components.
Type of Facility: Corium
SIMECO
Organization:
KTH
Type:
Corium
Description:

The SIMECO (SImulation of MElt COolability) test facility consists of a slice type vessel, which includes a semi-circular section and a vertical section, representing the lower head of the reactor vessel. The size of the facility is scaled to be 1/8 of prototypic PWR type reactors.