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67 results recovered

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Type of Facility: Thermal Hydraulics
HIPE
Organization:
LUT
Type of Facility:
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
PCCS
Organization:
LUT
Type of Facility:
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 of Facility:
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
PACTEL
Organization:
LUT
Type of Facility:
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
PWR PACTEL
Organization:
LUT
Type of Facility:
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.
New activities coming soon
Date of Activity:
30/09/2015
Description:

New activities related with Nuclear Safety research will be soon published in the new STRESA website.
New activities coming soon
Date of Activity:
15/03/2015
Description:

STRESA related activities are coming. Check frequently this website to be up to date!
Launching of the New STRESA
Date of Activity:
31/10/2014
Description:

The new STRESA becomes public replacing the previous version.
Information system testing meeting
Date of Activity:
16/09/2014 to 26/09/2014
City / Location:
Petten
Address:
Westerduinweg 3, NL-1755 LE Petten, The Netherlands
Description:

Meeting to evaluate the status of the information system and the problems encountered.
New STRESA information system
Date of Publication:
16/09/2014
Type of Facility: Thermal Hydraulics
LOBI
Organization:
European Commission
Type of Facility:
Thermal Hydraulics
Description:

The LOBI Project originated from a reactor safety research and development contract between the European Commission and the former Bundesminister für Forschung und Technologie of the Federal Republic of Germany.
Type of Facility: Source Term
CODEX
Organization:
MTA-EK
Type of Facility:
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: Source Term
VERDON
Organization:
CEA
Type of Facility:
Source Term
Description:

VERDON programme has been launched by the CEA as a follow-up of VERCORS programme.
Type of Facility: Source Term
RUTHENIUM
Organization:
IRSN
Type of Facility:
Source Term
Description:

No description available.
Type of Facility: Source Term
VERCORS
Organization:
IRSN
Type of Facility:
Source Term
Description:

The first tests were the HEVA series conducted between 1983 and 1989 where, with maximum temperatures restricted to 2100K, the main objective was to generate information on release of volatile FPs from UO2 fuel.
Type of Facility: Source Term
PHEBUS
Organization:
IRSN
Type of Facility:
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: Source Term
CHIP
Organization:
IRSN
Type of Facility:
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 of Facility:
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
PECA
Organization:
Ciemat
Type of Facility:
Source Term
Description:

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

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