Facilities


27 results recovered
Type of Facility: Thermal Hydraulics
ARISG
Organization:
Ciemat
Type:
Thermal Hydraulics
Description:

ARIGS is one of the programs on the aerosol retention on the tubes surrounding the breach within the secondary side of the steam generator in the absence of water. Its development has been internationally framed within the EU-SGTR and the ARTIST programs.
Type of Facility: Source Term
Becarre
Organization:
IRSN
Type:
Source Term
Description:

Characterisation methods:

Type of Facility: Source Term
CAIMAN
Organization:
IRSN
Type:
Source Term
Description:

Iodine is a fission product of major importance, because volatile species can be formed under severe nuclear reactor accident conditions, and may potentially be released into the environment, leading to significant radiological consequences.
Type of Facility: Containment
CARAIDAS
Organization:
IRSN
Type:
Containment
Description:

In order to comply with experimental device design requirements, different devices were developped, tested and set up on CARAIDAS:
Type of Facility: Source Term
CHIP
Organization:
IRSN
Type:
Source Term
Description:

This programme is dedicated to studying iodine chemistry under thermal non equilibrium (impact of chemical kinetics) in the primary cooling system in the event of a core meltdown accident in a water reactor.
The CHIP programme follows two axes which respectivly aims to:
Type of Facility: Source Term
EMAIC
Organization:
IRSN
Type:
Source Term
Description:

This emission has an impact on the iodine chemistry (AgI) and on the behavior of aerosols in the reactor primary circuit and in the containment. The presence of control rod material influences the source term potentially present in a PWR containment and likely to in the atmosphere.
Type of Facility: Source Term
Epicur
Organization:
IRSN
Type:
Source Term
Description:

This programme will help to better estimate the quantity of radioactive iodine released during a core meltdown accident taken into account when elaborating specific emergency plans.
Type of Facility: Source Term
HEVA
Organization:
IRSN
Type:
Source Term
Description:

HEVA programme started a series of fission-product release experiments, which have been continued with the VERCORS programme. HEVA and the three VERCORS (RT and HT) series represent a total of 28 tests.
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: Source Term
ISTP
Organization:
IRSN
Type:
Source Term
Description:

SOURCE TERM is an international research programme carried out by IRSN and CEA (Commissariat à l’Energie Atomique) with the support of Electricité de France, the European Commission, the US Nuclear Regulatory Commission (US), GDF/ SUEZ/ Tractebel (Belgium), Atomic Energy Canada Limited (Canada),

Type of Facility: Source Term
MOZART
Organization:
IRSN
Type:
Source Term
Description:

Mozart program to determine the air-oxidation kinetics of zirconium alloys at high temperature.
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: Source Term
PARIS
Organization:
IRSN
Type:
Source Term
Description:

In case of a hypothetical severe accident in a nuclear LWR (light water reactor), the high radiation fields reached in the reactor containment building due to the release of fission products from the reactor core could induce air radiolysis.
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: Corium
PEARL
Organization:
IRSN
Type:
Corium
Description:

In case of prolonged loss of cooling accident, the fuel rods of the core of a pressurized water reactor (PWR) will be damaged, and will collapse to form what is called a "debris bed", i.e.
Type of Facility: Source Term
PECA
Organization:
Ciemat
Type:
Source Term
Description:

Steam generator reliability and performance are serious concerns in the operation of pressurized water reactors.
Type of Facility: Source Term
PHEBUS
Organization:
IRSN
Type:
Source Term
Description:

Since the core meltdown accident in the Three Mile Island reactor in 1979, a series of experimental safety research programmes has been conducted by a number of international research organisations, including the IRSN, which manages the European SARNET network.
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: Corium
PRELUDE
Organization:
IRSN
Type:
Corium
Description:

The tests conducted in the PRELUDE facility help to validate key technical options for PEARL:
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.

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