Within the framework of the arrangement on the safety research participation and the technical exchange among the Unites States, Japan, and the Federal Republic of Germany (2D/3D-Program) the BMFT is sponsoring experimental and analytical investigations of thermalhydraulic phenomena during a loss-of-coolant-accident of a pressurized light water reactor. The tasks of the research program BMFT No. 1500808 are the parallel and complementary, analytical and experimental investigations of phenomena during the end of blowdown, the refill and the reflood phases of a LOCA, to assist the development of advanced computer code systems. The program consists of the following items: - A contribution to qualify the available data of measurements of UPTF-t...
The document deals with the description of results obtained by the Relap5 code in the post-test simu...
Im Bericht wird die Nachrechnung von insgesamt drei Versuchslaeufen des Versuches UPTF-TRAM A2 mit d...
To facilitate nuclear technology with high-temperature reactors without any risk of serious accident...
In the framework of the external validation of the thermohydraulic code ATHLET Mod 1.2 Cycle C, whic...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
This report deals with a CORA-9 post-test-calculation with the computer-code RELAP5/SCDAP Mod.2.5 Ve...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
The LOBI project has been carried-out in the framework of the European Commission Reactor Safety Re...
The thermal hydraulic and SFD (Severe Fuel Damage) best estimate computer modelling code SOCRAT/V3 w...
The aim of the Phébus Fission Product (FP) experimental program is to study the degradation phenomen...
The present work is finalized to investigate the E2.2 thermal-hydraulics transient of the PKL III fa...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
Degradation of B_4C absorber rods during a beyond design accident in a nuclear power reactor may be ...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
The document deals with the description of results obtained by the Relap5 code in the post-test simu...
Im Bericht wird die Nachrechnung von insgesamt drei Versuchslaeufen des Versuches UPTF-TRAM A2 mit d...
To facilitate nuclear technology with high-temperature reactors without any risk of serious accident...
In the framework of the external validation of the thermohydraulic code ATHLET Mod 1.2 Cycle C, whic...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
This report deals with a CORA-9 post-test-calculation with the computer-code RELAP5/SCDAP Mod.2.5 Ve...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
The LOBI project has been carried-out in the framework of the European Commission Reactor Safety Re...
The thermal hydraulic and SFD (Severe Fuel Damage) best estimate computer modelling code SOCRAT/V3 w...
The aim of the Phébus Fission Product (FP) experimental program is to study the degradation phenomen...
The present work is finalized to investigate the E2.2 thermal-hydraulics transient of the PKL III fa...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
Degradation of B_4C absorber rods during a beyond design accident in a nuclear power reactor may be ...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
The document deals with the description of results obtained by the Relap5 code in the post-test simu...
Im Bericht wird die Nachrechnung von insgesamt drei Versuchslaeufen des Versuches UPTF-TRAM A2 mit d...
To facilitate nuclear technology with high-temperature reactors without any risk of serious accident...