Beneficiary Organisation details
State Office for Nuclear Safety (Czech Republic)
http://www.sujb.cz
Nuclear Regulatory Agency (Bulgaria)
http://www.bnsa.bas.bg
Hungarian Atomic Energy Authority
http://www.haea.gov.hu
Nuclear Regulatory Authority of the Slovak Republic
http://www.ujd.gov.sk
Project Aims

• The first objective of the project was to contribute to the establishment of a VVER specific database by generation of experimental data from the PMK-2 and the ISB integral test facilities representing, respectively, the Russian-design VVER-440 and VVER-1000 nuclear power plants. Logically, the selected tests should fit in the "white spots" of the OECD defined cross-reference matrices. They should also respond to utility concerns related to the analysis work to support EOP development;
• The second objective of the project was a contribution to the validation of European Thermalhydraulic System Codes for VVER applications by performing post-test calculations and verifying the correct simulation of specific thermalhydraulic phenomena with respect to the experiment.

The project consisted of the following tasks:
Experimental area:

• Modification, respectively upgrading by advanced instrumentation of the PMK-2 test facility;
• Performance of the experiments on the PMK-2 and ISB test facilities according to the validation matrix with special attention to accident management (AM) measures.

Analytical area:

• Extension of the validation matrix to include AM procedures;
• Clarification of scaling effects by means of data and results of ISB- VVER (according to VVER-1000) and PMK-2 /PACTEL (according to VVER-440);
• Verification of the European ATHLET and CATHARE codes.

Project Results

• Taking into account the Beneficiaries needs for emergency operating procedures (EOP) development and the possibilities offered by the installation, the following three tests were performed on the PMK-2 test facility:
  • Test N° 1: stationary test addressing energy transport in the steam generator with lowered secondary side water level;
  • Test N° 2: 0.5% cold leg break overfed by HPIS;
  • Test N° 3: 7.4% cold leg break without HPIS, with secondary bleed and primary B&F.
• The test performed on the ISB test facility is a counterpart of the second PMK-2 test to show the impact of design differences between VVER-440 and VVER-1000 for an identical transient type:
  • Test N° 1: 0.5% cold leg break overfed by HPIS.

The project was completed and contributed to the establishment of a VVER specific experimental database. The suitability of the European thermalhydraulic codes ATHLET and CATHARE for VVER applications was verified by comparing their prediction against the experimental results. The scaling effect was addressed by performing the PMK-2 test N°2 and N°3 scenario calculations on the PACTEL and VVER models.
Further Project Results
a) See attached file;
b) Further information on the project results could be sought from the beneficiary organisations.