Banyuk vver 2010


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Banyuk vver 2010

  1. 1. Materials of equipment for reactor plants V-320 and V-491 Banyuk G.F., Ryzhov S.B., Mokhov V.А., Piminov V.А. International Topical Meeting VVER 2010. Experience & Perspectives 01 – 03 November 2010 Prague, Czech Republic
  2. 2. Units with VVER-1000 02 Country Number of Units Russian Federation 7 (VVER-1000/320) + 3 (VVER-1000/small series) Czech Republic 2 (VVER-1000/320) Bulgaria 2 (VVER-1000/320) Ukraine 11 (VVER-1000/320)+ 2 (VVER-1000/small series) China 2 (VVER-1000/V-428)
  3. 3. Units of AES-2006 design under construction 03 NPP Number of Units Novovoronezh-2 (V-392М) 2 Leningrad-2 (V-491) 2 Baltic NPP (V-491) (preparation for construction) 2
  4. 4. Main equipment of reactor plant 04 Reactor pressure vessel and top head Stream generator Pressurizer ECCS hydroaccumulator Pipelines (MCP)
  5. 5. Reactor plant 05
  6. 6. Reactor pressure vessel 06 Parameter Value V-320 V-491 Length, mm 10897 11185 Inner diameter, mm 4150 4250 Wall thickness in the belt line region, mm 192,5 197,5 Mass, t 320 330
  7. 7. Reactor pressure vessel 07 Additional requirements for materials are caused by: the stronger requirements for equipment and high thermal power as compared with those for a commercial Unit:  service life (60 years) and life (fuel cycle 8400 h) are extended;  primary and secondary coolant (pressure and temperature) parameters are increased
  8. 8. Reactor pressure vessel 08 Implementation of the measures aimed at improvement of brittle fracture resistance (BFR) of reactor vessels:  decrease in radiation embrittlement of RPV materials;  decrease in loads onto RPV under pressurized thermal shocks;  improved monitoring of changes in RPV material properties.
  9. 9. Reactor pressure vessel 09 Component Grade of steel RP V-320 RP V-491 Supporting shell. Cylindrical upper and lower shells 15Х2НМФА-А 15Х2НМФА class 1 Shells of nozzle area 15Х2НМФА-А Bottom head, flange 15Х2НМФА
  10. 10. Ni influence on radiation embrittlement of reactor pressure vessel steel Surveillance testing results and the results of research programs for VVER-1000 RPV materials have shown, that radiation embrittlement essentially depends on the nickel and manganese content 010
  11. 11. Decrease in radiation embrittlement of RPV materials 011 Chemical composition of RPV base metal (supporting and core shells) Grade of steel (RP type) Chemical composition, % C Si Mn Cr Ni Mo V Calc. 15Х2НМФА-А (В-320) 0.13-0.18 0.17-0.37 0.30-0.60 1.8-2.3 1.0 – 1.5 0.5-0.7 0.10-0.12 15Х2НМФА class 1 (В-491) 1.0 – 1.3 Grade of steel (RP type) Chemical composition, % Cu S P As Co Sb Sn Р + Sb + Sn No more than 15Х2НМФА-А (В-320) 0.10 0.006 0.008 0.010 0.03 0.005 0.005 - 15Х2НМФА class 1 (В-491) 0.06 0.007 0,012
  12. 12. Decrease in radiation embrittlement of RPV materials 012 Chemical composition of RPV welds metal (welds of core range) Welding wire, flux (RP type) Chemical composition, % C Si Mn Cr Ni Mo Ti Св-12Х2Н2МАА, flux ФЦ-16А (В-320) 0.04-0.10 0.15-0.45 0.65-1.10 1.4-2.1 1.2 – 1.9 0.45-0.75 - 0.45-1.10 1.2-2.0 1.0 – 1.3 0.40-0.75 0.01-0.06 Св-09ХГНМТАА-ВИ, flux НФ-18М (В-491) Welding wire, flux (RP type) Chemical composition, % Co S P Cu Sb Sn As No more than Св-12Х2Н2МАА, flux ФЦ-16А (В-320) 0.02 0.015 0.012 0.10 0.008 0.001 0.010 Св-09ХГНМТАА-ВИ, flux НФ-18М (В-491) 0.08 Тко of core weld metal: В-320 ≤ 0 0 С В-491 ≤ minus 15 0 С
  13. 13. Decrease in radiation embrittlement of RPV materials 013 Decrease in neutron fluence Fluence decrease is implemented due to increase in the RPV diameter and core arrangement (FA placing) with reduced neutron leakage Maximum values of neutron fluence with an energy above 0.5 MeV for various points Location Design data of neutron fluence (F ∗ 1023 ), n/m2 В-320 (40 years) В-491 (60 years) Core top (supporting shell) 2.44 1.28 Base metal in the place of max. neutron fluence 5.7 4.22 Weld No. 2 5.7 4.06 Weld No. 3 4.5 3.58
  14. 14. Decrease in radiation embrittlement of RPV materials 014 Tk calculation results Location Tk, 0 C В-320 (40 years) В-491 (60 years) Core top (supporting shell) 42 29 Base metal in point of max neutron fluence 64 55 Weld No. 2 77 69* Weld No. 3 71 66* * - without regard for Тко ≤ minus 15°С
  15. 15. Decrease in loads onto RPV under PTS 015 Decrease in loads is achieved due to limitation of the minimum water temperature in the emergency core cooling system Decrease in loads on RPV under PTS Reactor plant type Temperature of ECCS water, 0 C, not less than V-320 10 V-491 20
  16. 16. Improved monitoring of changes in RPV material properties 016 Improvement is achieved due to change in location of surveillance specimen casks. In RP V-320 the surveillance specimen casks were located in the channels of the reactor core baffle. In RP V-491 the casks are placed directly on the inside wall of the reactor pressure vessel in the place of maximum fluence
  17. 17. Monitoring of RPV metal state during operation (surveillance program) Irradiated surveillance sets are located opposite to the core and fixed directly on the RPV wall. 017
  18. 18. Surveillance specimens Surveillance specimen program for RPV of RP V-491 defines: 1.Irradiated sets (materials, number and date of removal). 2.Temperature sets (материалы, number and date of removal). 3.Test sets. 4.Scheme for cutting of specimens. 5.Number of specimens for each type of tests. 6.Type of specimens. 7.Quality Assurance Program. 018
  19. 19. Surveillance specimens 019 Basic requirements for fabrication of surveillance specimens Surveillance specimens for in-service inspection of change in RPV metal properties shall be fabricated from:  base metal;  weld metal;  HAZ metal. Billets of the base metal surveillance specimens shall be cut out of the test ring of the standard shells after basic heat treatment. The billets shall be subject to heat treatments under the modes identical to heat treatment modes of the shell, from which the test ring is cut out, in the course of the vessel manufacture.
  20. 20. Surveillance specimens 020 Basic requirements for fabrication of surveillance specimens Billets of specimens of weld metal and HAZ metal shall be cut out of the circular welded sample, made of metal cut from one of the RPV shells. The sample shall be of the same thickness and the same grooving as the RPV welds. The circular welded sample shall be made under the same modes and using the same welding process and welding materials of the same lots as the tested RPV welds. The sample shall be subject to the same complex of heat treatments as the RPV welds to be tested.
  21. 21. The first AES-2006 RPV for Novovoronezh-2 NPP was manufactured at the Izhora plant in this year The second AES-2006 RPV for Novovoronezh-2 is planned in the next year 021
  22. 22. Main coolant pipeline 022 Tubes for manufacture of MCP Technical conditions TU 108.1197-83 (the Manufacturer - «EUROTUBE GmbH») Outer diameter, mm Inner diameter, mm Wall thickness, mm Maximum length, mm Thickness of cladding layer, mm 990 850 70 8400 5 1130 990 70 8400 5
  23. 23. Main coolant pipeline 023 Materials Chemical composition of the base metal of MCP tubes Grade of steel Content of elements, % C Si Mn Ni Mo V S P Cr Cu 10ГН2МФА 0.08- 0.12 0.17- 0.37 0.70- 0.90 1.70- 2.00 0.40- 0.60 not more than 0.04 0.020 0.020 0.30 0.30
  24. 24. Main coolant pipeline 024 Materials Chemical composition of deposited corrosion-resistant coating 03Х22Н11Г2Б Content of element, % C Si S P Cu Co N Mn Cr Ni Nb not more than 1.00- 2.50 17.50- 20.50 8.50- 11.0 0.70- 1.000.05 1.00 0.02 0.03 0.30 0.02 0.05
  25. 25. Regulatory requirements 025 Regulations for design and safe operation of nuclear plant equipment and pipings (PNAE G -7-008-89). Regulations for strength calculation of equipment and pipings of nuclear power plants (PNAE G -7-002-86). Equipment and pipings of nuclear power plants. Welding and cladding. General provisions (PNAE G -7-009-89). Equipment and pipings of nuclear power plants. Welded joints and claddings. Rules of inspection (PNAE G -7-010-89).
  26. 26. Regulatory requirements 026 Guiding technological document. Equipment and pipings of nuclear power plants. Welding, cladding and heat treatment of welded joints of components of steels of grades 10ГН2МФА, 10ГН2МФАЛ, 15Х2НМФА, 15Х2НМФА-А, 15Х2НМФА class 1 (RTD 2730.300.02.91). Standardized control procedures for inspection of base materials (semi-products), welded joints and claddings of nuclear power plant equipment and pipings: Ultrasonic test. Inspection of base materials (semi-products) (PNAE G -7-014-89). Magnetic particle test (PNAE G -7-015-89). Visual and measurement check (PNAE G -7-016-89).
  27. 27. Regulatory requirements 027 Radiographic examination (PNAE G -7-017-89). Penetrant test (PNAE G -7-018-89). Check of leak-tightness. Gas and liquid methods (PNAE G -7-019-89). Ultrasonic test. Part II. Inspection of welded joints and claddings (PNAE G -7-030- 91). Standardized control procedures for inspection of base materials (semi-products), welded joints and claddings of nuclear power plant equipment and pipings Ultrasonic test. Part III. Measurement of thickness of monometals, bimetals and corrosion-resistant coatings (PNAE G -7-031-91). Ultrasonic test. Part IV. Inspection of welded joints of austenitic steels (PNAE G -7-032-91).
  28. 28. Welcome to the 7th International Scientific and Technical Conference “Safety Assurance of NPP with VVER” which will take place at OKB “GIDROPRESS”, Podolsk, Russia on 17-20 May, 2011 More details at 028