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system computer code

ALEXANDROV RESEARCH INSTITUTE OF TECHNOLOGY. SOSNOVY BOR, LENINGRAD REGION, RUSSIA. Development status and. applications of the. KORSAR. system computer code. Yu.A. Migrov, Yu.V. Yudov. 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety

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system computer code

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  1. ALEXANDROV RESEARCH INSTITUTE OF TECHNOLOGY SOSNOVY BOR, LENINGRAD REGION, RUSSIA Development status and applications of the KORSAR system computer code Yu.A. Migrov, Yu.V. Yudov 17th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29,2007 Yalta, Crimea, Ukraine

  2. 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine Current importance of domestic best estimate computer code development KORSAR • Life extension and improvement of operating NPP units • Development of the new generation NPP designs with passive safety systems • Construction of Russian-designed NPPs abroad 2

  3. The main characteristics and design schedule of the basis versions KORSAR 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine Two-fluid model of the system thermal hydraulics KORSAR/V1  Point model of the reactor kinetics Design schedule1996-2001  Accounting for liquid absorber Models for the equipment components of the reactor heat exchange loops Models for the reactor control system components Supplementary features to KORSAR /V1 KORSAR/V2 Spatial model of the reactor kinetics Design schedule1997-2002 Supplementary feature to KORSAR /V1, KORSAR /V2 KORSAR/V3 Accounting for non-condensable gases Design schedule1999-2002 Models of the STU equipment components 3

  4. KORSAR Functional modules SYSTEM THERMOHYDRAULICS MODULE SPECIALIZED PROGRAM MODULES SUPPORT PROGRAM MODULES WATER AND STEAM PROPERTIES CLOSING RELATIONS 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 4

  5. KORSAR Set of specialized modules I version Pressurized steam-water vessel Reactor neutron kinetics Heat transfer structures Free-level tank Centrifugal pump Accumulator Valves 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine DEVELOPED AND INTRODUCED INTO SERVICE IN 1998 5

  6. KORSAR Interfacial heat transfer Interfacial shear stress F F Drop-annular Drop-annular bubbly slug bubbly slug dispersed dispersed Fcr2 Fcr2 Fcr2 Fcr2 stratified stratified - closing relations are taken from the published data - original technique for calculating closing relations 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 6 • Two-phase flow patterns in horizontal tubes

  7. Verification activities were co-ordinated by Minatom OCRK • Participation in verification activity of specialists from other Minatom organizations (beside NITI), RAS institutes, and universities • Making the most use of Russian Standard Safety Problems • Making use of ISP available in Russia • Wide use of cross verifications 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 7 KORSAR/V1 Characteristics of verification procedure

  8. LIST of integral LBLOCA and SBLOCA simulation experiments for VVER 8

  9. Integral system verification at the PACTEL test facility ISP33 Collapsed level in Pressurizer, kPа Pressure drop in HL of Loop 1,kPа Pressure,МPа Pressure drops in Reactor Model , kPа Coolant flow rate in Downcomer,кg/s Pressure drop in HL of Loop 2,kPа ExperimentCalculation 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 9

  10. SAPFIR-KORSAR KORSAR/V2 SAPFIR RC КАRТА 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 10 Software configuration Neutronics – Thermal-Hydraulics Calculation

  11. AER-2 Neutron power KORSAR Power, MW Time, s 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 11 AER-2. Results of static calculation

  12. Relative Power Distribution in Fuel Assemblies (Rostov-1 NPP) 77 78 SAPFIR_97 & RC 78 104 92 Т=196.5 eff. day EXPERIMENT 106 93 106 93 BIPR 95 102 94 95 103 97 95 103 96 111 96 108 94 109 96 110 97 109 96 110 96 92 100 113 96 102 98 113 96 103 94 98 113 96 103 93 116 100 111 95 104 77 114 98 109 95 106 78 115 98 109 95 106 78 114 100 113 99 109 94 101 111 97 110 98 108 94 102 111 97 110 98 108 94 102 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 12

  13. 1.02 272 Experiment, loop 1 Relative neutron power of core Experiment, loop 5 268 1.01 Temperature, C. 264 Power, r.u. 260 1 256 Coolant temperature in cold legs of loops with RCP in operation 0.99 252 0 10 20 30 40 KORSAR 0 40 80 120 160 200 TRAP Experiment 2.08 1.2 Revolutions of RCP-3 in coastdown mode 2.04 2 0.8 Revolutions, r.u. 1.96 Distance from core bottom,m. 1.92 0.4 1.88 Position of control rods 1.84 0 0 10 20 30 40 0 40 80 120 160 200 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 13 KORSAR ATWS with RCP coastdown NORD NPP (Germany)

  14. Characteristics of modeling non-condensing gas (NG) behavior • The number of components – 4 (N2, H2, O2, He) • Carry-over in the liquid and gas phases • Thermal and mechanical equilibrium of NG components and carrier phases • NG effect on mass and energy balance of the liquid phase is not accounted for • Effect of non-condensing gases on heat transfer • NG sources: • metal-steam reaction • gas release from liquid phase • radiolysis of the coolant components • ingress from external sources 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 14 KORSAR/V3

  15. 420 Ti Ts,v 400 Tw Run Air mass Total heat fraction flux Δ% 380 Temperature, K 1-1-3R 03347334003+ 1.6 2-1- 5 0.0592795826852- 4 2-1- 8R 0.1482127024607+15.7 360 2-1-13 0.3961764019948+13.1 experiment, Wcalculation, Werror,% 340 Z,m 2.5 0 0.5 1 1.5 2 Temperature distribution along the channel length 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 15 Verification of the model against experiments of Kuhn et al. KORSAR/V3

  16. L-1070 L-1070 P= 0.5 MPa P= 0.2 MPa Test facility SG Test facility SG experiment experiment calculation calculation Power, MW Power, MW Relative partial pressure of gas Relative partial pressure of gas L-1070 P= 2.0 MPa Test facility SG Power, MW experiment calculation Relative partial pressure of gas 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 16

  17. c / 0.25 g k + 2 0 % , 3 0 0.2 1 x ) x n u o l f 0.15 i t s a l s u a c m l 0.1 a n c ( o i t a 0.05 r o p a v 0 E 0 0.05 0.1 0.15 0.2 0.25 3  E v a p o r a t i o n m a s s f l u x 1 0 , k g / c Parameters of experiments P = 105 Pa 0.8 ≤ Gg≤ 3.4 kg/s 0.25 ≤ Xa ≤ 1 370 ≤ Tgin ≤ 705 K 3 ≤ Gf ≤ 20 gm/s 305 ≤ Tf ≤ 370 K (d = 22.9 mm l = 0.946 m) ( e x p e r i m e n t ) 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 17 Verification of the model against experiments of Cairns and Roper

  18. 17th SYMPOSIUM of AERon VVER Reactor Physics and Reactor SafetySeptember 24-29,2007 Yalta, Crimea, Ukraine 18 Conclusions • The KORSAR system code is a new generation software tool designed for computer-based analysis of VVER dynamics. It is characterized by enhanced versatility, high level of physical-mathematical models, user-code friendly interface, and flexible topology. • The first base version KORSAR /V1.1 has been certified at Gosatomnadzor (2003) and put in trial run at OKB “Gidropress”, SPbAEP and is now used in design calculations for VVER safety analyses. • The completion of the second and third base versions development and verification will much extend the KORSAR code application area for the VVER NPP safety analysis purposes.

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