The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the integral test facility PMK-2 in Budapest. It was a 3.2 mm break on the downcomer head. The high pressure injection cooling was assumed to be not available. As an accident management measure bleed and feed on the secondary side of the steam generator was applied. Research Center Rossendorf contributed to the experiment of SPE-4 by supplying needle shaped conductivity probes for the measurement of local void fractions in the primary circuit of the PMK-II test facility. In the course of the standard problem exercise No. 4 RCR contributed with posttest calculations using the thermalhydraulic code ATHLET. The report comprises a description of the init...
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 QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
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...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
In the framework of the computer code assessment programme for the VVER-440 type Paks Nuclear Power ...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The RELAP/MOD3.2 computer code has been assessed using an 11% upper plenum break experiment in the P...
Within the framework of the arrangement on the safety research participation and the technical excha...
Selected experimental test facilities located in Eastern European Countries have been assessed with ...
Thepresent paper dealswith the analytical study of the PKL experiment G3.1 performed using the TRACE...
This report deals with a CORA-9 post-test-calculation with the computer-code RELAP5/SCDAP Mod.2.5 Ve...
The separate effect UPTF TRAM Test A2 consisting of six runs was designed to investigate flow regime...
In the framework of the external verification of the fluiddynamic computer code ATHLET developed by ...
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 QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
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...
The experiment to the IAEA standard problem exercise No. 4 was carried out in April 1993 on the inte...
In the framework of the computer code assessment programme for the VVER-440 type Paks Nuclear Power ...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The RELAP/MOD3.2 computer code has been assessed using an 11% upper plenum break experiment in the P...
Within the framework of the arrangement on the safety research participation and the technical excha...
Selected experimental test facilities located in Eastern European Countries have been assessed with ...
Thepresent paper dealswith the analytical study of the PKL experiment G3.1 performed using the TRACE...
This report deals with a CORA-9 post-test-calculation with the computer-code RELAP5/SCDAP Mod.2.5 Ve...
The separate effect UPTF TRAM Test A2 consisting of six runs was designed to investigate flow regime...
In the framework of the external verification of the fluiddynamic computer code ATHLET developed by ...
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 QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
In the framework of the external validation of the thermohydraulic code ATHLET Mod 1.2 Cycle C, whic...