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System computer code 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine Development status.

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Presentation on theme: "System computer code 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine Development status."— Presentation transcript:

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

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

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

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

5 DEVELOPED AND INTRODUCED INTO SERVICE IN 1998 Centrifugal pump Pressurized steam-water vessel AccumulatorAccumulator Free-level tank ValvesValves Reactor neutron kinetics Heat transfer structures I version Set of specialized modules 5 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine

6 Two-phase flow patterns in horizontal tubes - closing relations are taken from the published data - original technique for calculating closing relations Interfacial heat transfer Interfacial shear stress 6 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine bubbly slug dispersed Drop- annular stratified F F cr 2 bubblyslug dispersed Drop- annular stratified F F cr 2

7 Characteristics of verification procedure 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 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 7

8 LIST of integral LBLOCA and SBLOCA simulation experiments for VVER Test facilityExperiment typeExperiment name SB LBLOCASB/1 PSB-VVER LBLOCAGT-2x25-02 SBLOCAVKS SBLOCAGZ SBLOCAPV SBLOCAPP SBLOCAXT SBLOCAXT SBLOCAXT SBLOCAXT SBLOCAUP ISB-VVER SBLOCASPB-1 SBLOCASPB-2 SBLOCASPB-3 IST(EC) NCNC-05/12-95/11 KEDR NCKE-1 NCKE-2 PMK-NVH SBLOCASPE-1 SBLOCASPE-2 SBLOCASPE-4 PACTEL NCISP-33 BETHSY SBLOCAISP-27 SBLOCAISP-38 8

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

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

11 ParameterDYN3DBIPR-8HEXTRANKORSAR K 0 eff 0, , , , K 1 eff 1, , , , ,% 0,97551,01431,00691,0147 3,983,224,02 AER-2 Power, MW Neutron power Time, s KORSAR AER-2. Results of static calculation 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 11

12 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 12

13 ATWS with RCP coastdown NORD NPP (Germany) KORSAR TRAP Experiment 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 13

14  The number of components – 4 (N 2, H 2, O 2, 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  gas release from liquid phase  radiolysis of the coolant components  ingress from external sources  metal-steam reaction  NG sources: Characteristics of modeling non-condensing gas (NG) behavior Characteristics of modeling non-condensing gas (NG) behavior 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 14

15 Verification of the model against experiments of Kuhn et al. Temperature distribution along the channel length experiment, W calculation, W error,% R Run Air mass Total heat fraction flux Δ% R TiTi T s,v TwTw Temperature,  K Z,m 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 15

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

17 Verification of the model against experiments of Cairns and Roper Parameters of experiments P = 10 5 Pa 0.8 ≤ G g ≤ 3.4 kg/s 0.25 ≤ X a ≤ ≤ T gin ≤ 705 K 3 ≤ G f ≤ 20 gm/s 305 ≤ T f ≤ 370 K (d = 22.9 mm l = m) Evaporation mass flux  10 3, kg/c (experiment) E v a p o r a t i o n m a s s f l u x x 1 0 3, k g / c ( c a l c u l a t i o n ) + 20 % 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 17

18  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. Conclusions Conclusions 17 th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine 18


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