The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose of this paper is to summarize the main findings from the execution of a wide-range analysis focused on AM in VVER-1000 with main regard to the qualification of computational tools and the proposal for an optimal AM strategy for this kind of NPP.
SOMMARIO. SBO and SBLOCA .................................. 48 4.2.4.1.3. Results of the analysis ......................................................... 49 4.2.4.1.4. Decay heat power ................................................................ 49 4.2.4.1.5. Hot rod temperature............................................................. 55 4.2.4.1.6. Analysis of the results .......................................................... 57 4.2.4.1.7. Conclusion ........................................................................... distribution..................... 59 4.2.4.2.3. Model and calculation cases................................................ 60 4.2.4.2.4. Evaluation of the cell probability .......................................... 61 4.2.4.2.5 LIST OF SYMBOLS U (1979) with 1973 ...................................................................................................... 70 Fig. 55 -LARGE reactor sin, 100 s, produced and absorbed power versus height fine model....................................................................................................... 70 Fig. 56 -CHF comparison, 7 MPa (RELAP5/Mod 2)............................................. 73 Fig. 57 -CHF Comparison 3 MPa (RELAP5/Mod2) .............................................. 73 Fig. 58 -LOFT: core cross flow model................................................................... 76 Fig. 59 -LOFT: core temperature .......................................................................... 76 Fig. 60 -LOFT: core mass flow ............................................................................. 77 Fig. 61 -PWR-1000: core cross flow model .......................................................... 78 Fig. 62 -PWR-1000: core temperature comparison.............................................. 79 Fig. 63 -PWR-1000 ...................................... 136 Fig. A.11 -Schematic processes in the Swedish reactor licensing program....... 137 Fig. A.12 -Schematic of steps in the Swedish reactor licensing program .......... 138 Fig. A.13 -VVER 1000, Steady State: Up and SGs (1 to 4) pressure ................ 143 Fig. A.14 -VVER 1000, Steady State: Core inlet mass flowrate......................... 144 Fig. A.15 -VVER 1000, Steady State: Core and SG exchanged power ............. 144 Fig. A.16 -VVER 1000 1 (up to 11000s)........ 160 Fig. A.44 -Pressure in the upper plenum in the transient 2 (up to 8000s).......... 160 Fig. A.45 -Pressure in the upper plenum in the transient 1 (up to 1200s).......... 161 Fig. A.46 -Pressure in the upper plenum in the transient 2 (up to 1200s).......... 161 Fig. A.47 -Model of the LOFT and PWR core..................................................... 163 XVIII LIST OF TABLES INTRODUCTIONSafety is an essential part for the peaceful use of nuclear power generation. The safety of nuclear power plants is based on the concept of defence in depth [1], Fig. 1, which indicates successive physical barriers (fuel matrix, cladding, primary system pressure boundary and ...
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