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Additional resources for Bubbler-Condenser-Related Research (csni-r2001-3)
0verall conclusions related to the understanding of the containment with Bubbler Condenser System Summarising the above discussions and observations the following conclusions and recommendations may be drawn with respect to the usefulness of the BCEQ Project and the complementary TSO activity: − It must be noted that only a small fraction of the contracted EREC test matrix had been executed before termination of the BCEQ Project. − The discussions of the main findings of tasks 2 and 4 of the BCEQ Project during the TAC meetings and the Support Group meeting in Berlin in April 2000 have evidenced contradictory points of view amongst the experts.
Jozsef Bajsz Head, Analysis and Development Section Paks Nuclear Power Plant Ltd. Pf. 71 H-7031 Paks Dr. Zsolt Téchy Project Manager, Nuclear Engineering Division Institute for Electric Power Research Co. (VEIKI) Gellérthegy utca 17 Pf. 80 H-1251 Budapest RUSSIAN FEDERATION Prof. Dr. Vladimir N. Blinkov Director Electrogorsk Research & Engineering Center on Nuclear Plant Safety (EREC) Bezymyannaya 6 Electrogorsk Moscow Region, 142530 Dr. Oleg Melikhov Head, Thermal-Hydraulics Division Electrogorsk Research & Engineering Center on Nuclear Plant Safety (EREC) Bezymyannaya 6 Electrogorsk Moscow region, 142530 40 NEA/CSNI/R(2001)3 Dr.
The discussions of the main findings of tasks 2 and 4 of the BCEQ Project during the TAC meetings and the Support Group meeting in Berlin in April 2000 have evidenced contradictory points of view amongst the experts. The main points of divergent opinions are related to the following items: 1. The primary purpose of thermal-hydraulic experiments in the area of nuclear safety was always to serve validation and verification of codes and/or code application concepts (the Analytical Simulation Models) which finally may be applied to predict thermal-hydraulic phenomena in full-size Nuclear Power Plants important for their reactor safety functions.