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Advanced Designs of VVER Reactor Plant


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Advanced Designs of VVER Reactor Plant

  1. 1. Advanced Designs of VVER Reactor Plant V.A. Mokhov VVER-2010. Experience & Perspectives 01-03 November 2010. Prague. Czech Republic
  2. 2. 2 What is VVER?  Pressurized light water reactor.  Loop-type reactor plant.  Horizontal steam generators.  Hexagonal fuel assemblies.  A high level of inherent safety.  49 Units under operation (about 1400 reactor-years of the total operating time). INTRODUCTION
  3. 3. 3 Current challenges INTRODUCTION  Competitiveness of nuclear power plants compared with fossil fuel power plants: extension of service life and increase in operability; implementation of load-follow conditions; reduction in capital costs and construction time, etc.;  Implementation of nuclear power plants of a wide power range of 300 – 1800 MWe;  VVER efficient use in a closed fuel cycle.
  4. 4. 4 Answer to the current challenges Development of advanced designs of generation 3+. The main trends of improvement are:  extension of the main equipment service life;  decrease in the metal consumption;  decrease in the RP dimensions (aimed at containment size decrease);  optimal use of the redundancy, independence and diversity principles in design of safety systems.  informatization of life cycle, introducing of datacentering technologies, 3D designing Development of VVER innovative designs of generations 3++ and 4. INTRODUCTION
  5. 5. 5 Development of VVER was initiated at OKB “GIDROPRESS” and RRC “Kurchatov Institute” in 1955. The first NPP with VVER (with power of 210 MW, el.) was commissioned at Unit 1 of NV NPP in 1964. Since that time the RP designs have been under continuous improvement, which is aimed at increasing safety, power, operational characteristics and economical efficiency of NPP with VVER. EVOLUTION OF VVER
  6. 6. 6 First designs of low and medium power (1955 – 1975) EVOLUTION OF VVER
  7. 7. 7 Designs of high-power (1966 – 2003) EVOLUTION OF VVER
  8. 8. 8 Modern designs (2000 – 2007) EVOLUTION OF VVER
  9. 9. 9 Advanced and innovative designs EVOLUTION OF VVER Abbreviations used: SLE – service life extended; COM – commissioning; CtP – concept proposal; D – design is developed; DCOM – decommissioned; UC – NPP under construction; UO – under operation.
  10. 10. 10 EVOLUTION OF VVER Modern NPPs with VVER-1000 reactor plant Iran “Bushehr” NPP China “Tianwan” NPP India “Kudankulam” NPP
  11. 11. 11 EVOLUTION OF VVER The basis of the evolutionary development and improvement of VVER is VVER-1200 RP of generation 3+ for AES-2006 being under construction at LNPP-2.
  12. 12. 12 References of design Development of design RP V-491 for LNPP-2 was started in 2007. VVER-1200 for AES-2006 AES-91 with V-428 ("Tianwan“ NPP) LNPP-2 with V-491 MIR-1200
  13. 13. 13 Main parameters of reactor plant VVER-1200 for AES-2006 Parameters V-428 VVER-1200 Reactor nominal thermal power, MW 3000 3200 Availability factor 0,8 0,9 Coolant pressure at the reactor outlet, MPa 15,7 16,2 Coolant temperature at the reactor inlet, о С 290 298,6 Coolant temperature at the reactor outlet, о С 320 329,7 Maximum linear heat rate, W/cm 448 420 Steam pressure at the outlet of SG steam header (absolute) MPa 6,27 7,0 Primary design pressure, MPa 17,64 17,64 Secondary design pressure, MPa 7,84 8,1 Maximum fuel burnup fraction over FAs in the FAs unloaded (in base equilibrium fuel cycle), MWD/kgU 49 до 70 Refueling period, month 12 12/(18-24) Time of fuel residence in the core, year 4 4/5
  14. 14. 14 VVER-1200 for AES-2006 Vessel Parameter Value VVER- 1200 VVER- 1000 (V-428) Length , mm 11185 11185 Inner diameter, mm 4250 4150 Wall thickness in the beltline region, mm 197,5 192,5 Mass, t 323 317
  15. 15. 15  Corridor arrangement of tube bundle;  Increase in vessel diameter: ID is increased from 4.0 to 4.2 m;  SG service life is extended to 60 years. VVER-1200 for AES-2006 Steam generator
  16. 16. 16 Fuel improvement VVER-1200 for AES-2006
  17. 17. 17 NPP safety  The basis for safety assurance is the high level of RP inherent safety.  The safety analyses performed for design and beyond design basis accidents showed that the established acceptance criteria are met.  Nomenclature and configuration of safety systems is necessary and sufficient for safety assurance of NPP, in line with the requirements of RF regulatory documents. VVER-1200 for AES-2006
  18. 18. 18 NPP safety (continued) Target value – frequency of severe damage of the core shall not exceed 10-5 (reactor·year)-1 By the results of PSA the frequency of severe damage of the core is: LNPP-2 5.9 10-7 (reactor·year)-1 VVER-1200 for AES-2006
  19. 19. 19 NPP safety (continued) VVER-1200 for AES-2006  Double protective envelope (containment), the internal containment has the controlled system of preliminary loading.  Four channels of active safety systems (4x100%) of improved arrangement and with a number of original solutions.  Maximum use of the approved technical solutions and equipment.  Special engineering measures in case of occurrence of beyond design basis accident: • device for corium localization (core catcher), • hydrogen recombiners, • passive heat removal system based on usage of passive principles (PHRS) for heat removal from SG and containment.
  20. 20. 20 Consortium participants MIR-1200 ŠKODA JS a.s. More than 50 years of activities in nuclear power industry. A partner of world nuclear companies and power societies.. One of the leading engineering and production companies all over the world The company made 21 sets of pressurized water reactors with power of 440 MW and 3 reactors with power of 1000 MW. JSC “ATOMSTROYEXPORT” The leading State Engineering company controlled by State Corporation “Rosatom”. ~ 20% of the competitive world market. Supply of NPPs of new generation completely meeting the international requirements and IAEA and EUR standards. OKB “GIDROPRESSS” Designs and production documentation for NPPs with VVER. Modernized designs notable for improved safety, reliability, efficiency and competitiveness.
  21. 21. 21 MIR-1200  Evolutionary design based on approved solutions with improved safety level (VVER-1000 for “Tianwan” NPP and VVER- 1200 for AES-2006).  Meets EUR requirements.  Construction license for two Units (LNPP-2).  Decision on construction of Baltic NPP.  Service life is 60 years.  Net energy power is 1113 МВт (el.)
  22. 22. 22 MIR-1200 Implementation of the project in Czech Republic  Localization of at least 70 % of supplies of equipment and services in Czechia;  Substantial portion of supplies and services from the Suppliers of Slovakia;  Bringing down the unemployment rate;  Substantial progress in technical education;  Standing a better chance for Czech and Slovak companies in participation in the projects, based on similar technology, in the third countries.
  23. 23. 23 The Project offers the specific participation of Czech and Slovak companies in the following activities  Supplies of civil structures;  Production of components (machine, electrical);  I&C;  Mounting;Mounting;  Commissioning work;Commissioning work;  Services for the Units under operation.Services for the Units under operation. MIR-1200
  24. 24. 24 VVER-600 design concept  Power is 600 MWel;  Two circulation loops;  Main equipment based on VVER-1200 (LNPP-2):  direct borrowing of equipment;  reference character;  regular manufacturing of equipment does not require considerable expenses.  Safety assurance in line with the requirements for NPP of generation 3+;  Design service life is 60 years;  Core melt retention in the reactor vessel during severe BDBA. VVER-600
  25. 25. 25 Main equipment layout VVER-600
  26. 26. 26 Main equipment layout (cont.) VVER-600 Ø36 m PressurizerPressurizer ECCS accumulator-1 RCP set Spent fuel pool Steam generator Reactor
  27. 27. 27 ECCS HA Main equipment layout (cont.) VVER-600 Passive heat removal system Main coolant pipeline Reactor PressurizerPressurizer Steam generator 2nd stage HA
  28. 28. 28 For the effective use of VVER in the closed nuclear fuel cycle a version is studied for the innovative core with the tight fuel rod grid VVER-600 SR (Generation 3++) Expected characteristics of fuel cycle: - conversion factor is about 0,7 - 0,8 (0,4 for VVER-1200); - consumption of natural uranium is about 130 t/GWe (197 t/GWe for VVER-1200)
  29. 29. 29 VVER-SCP (Generation 4) Innovative trend in development of VVER technology is RP VVER-SCP cooled with water of supercritical pressure. The given RP is a logic development of VVER connected with further increase in water parameters. Reactors cooled with water of supercritical pressure, SCWR, present one of options of the International Forum Generation IV.
  30. 30. 30 VVER-SCP (Generation 4) Main parameters: Thermal power, MW 3830 Electric power, MW 1700 Efficiency, % 43 Fuel UO2 +PuO2 Coolant water Pressure 24.5 MPa Inlet coolant temperature, °С 290 Outlet coolant temperature, °С 540 Conversion factor 0.9
  31. 31. 31 VVER-SCP (Generation 4) Main parameters of fuel assembly: Parameter Value Width across flats, mm 205 Quantity of fuel rods in FA, pcs. 252 Fuel rod diameter and cladding thickness, mm 10.7×0.55 Fuel pellet diameter, mm 9.4 Pitch of fuel rod triangular grid, mm 12 Quantity of guiding tubes for RCCA, pcs. 18 Central tube, pcs. 1 Diameter and thickness of guiding and central tubes, mm 12×0.55 Jacket thickness, mm 2.25
  32. 32. 32  OKB "GIDROPRESS" in cooperation with design and scientific organizations provides VVER evolutionary development to satisfy the latest requirements for NPP safety and economic efficiency.  The development of innovative designs for VVER of generation 3++ and 4 that would meet the up-to-date challenges of Russian and world-wide nuclear power engineering is in progress CONCLUSION
  33. 33. 33 Thank you for your attention!