Facilities


13 results recovered
Type of Facility: Corium
COLIMA
Organization:
CEA
Type:
Corium
Description:

Determination of the vaporization rate according to the composition and the thermodynamic conditions of the corium (with FP simulants) was the aim of the COLIMA (COrium LIquid and MAterials) experiments.
Type of Facility: Source Term
FIPRED-EQ
Organization:
ICN-Pitesti
Type:
Source Term
Description:

The Institute for Nuclear Research Pitesti (ICN) has as main activity objective the scientific research, the fundamental and applied technological development, the exploitation of its own research through technology transfer, design, investments, consultancy, expertise and technical specialized a
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: Corium
KROTOS
Organization:
CEA
Type:
Corium
Description:

The test section of the KROTOS facility consists of a stainless steel test section bolted to lugs welded on the inner side walls of a stainless steel pressure vessel.
Type of Facility: Containment
MISTRA
Organization:
CEA
Type:
Containment
Description:

The influence of containment sprays on atmosphere behaviour is being investigated both experimentally and theoretically. Experiments are being performed on the TOSQAN and MISTRA experimental facilities.
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
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: Containment
TOSQAN
Organization:
CEA
Type:
Containment
Description:

The experiment objective was to study the physical phenomena that affect hydrogen distribution in the reactor containment such as: steam wall condensation, heat mass and momentum exchanges with the sump or with the containment spray systems.
Type of Facility: Source Term
VERDON
Organization:
CEA
Type:
Source Term
Description:

VERDON programme has been launched by the CEA as a follow-up of VERCORS programme.
Type of Facility: Corium
VITI
Organization:
CEA
Type:
Corium
Description:

VITI (‘‘VIscosity Temperature Installation’’) experimental assembly: (1) VITI chamber, (2) graphite crucible, (3) ZrCcoating, (4) studied mixture, (5) graphite susceptor, (6) thermal shield, (7) support for crucible, (8) support for thermal shield, (9) inductance coil, (10) pyrometer – measure of
Type of Facility: Corium
VULCANO
Organization:
CEA
Type:
Corium
Description:

In the hypothetical case of a nuclear reactor severe accident, the reactor core could melt and form a mixture, called corium, of highly refractory oxides (UO2, ZrO2) and metallic or oxidized steel, that could eventually flow out of the vessel and mix with the basemat decomposition products (gener