Facilities


9 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: Source Term
HORIZON
Organization:
Fortum
Type:
Source Term
Description:

In severe accidents with primary-to-secondary leakages, the retention of fission products in horizontal steam generators is poorly understood.
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
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.