Current reactor technology, part III: Radek Škoda Czech Technical University Prague WNU SI 2010 Christ Church, Oxford

Transcription

1 Current reactor technology, part III: VVER RBMK Radek Škoda Czech Technical University Prague Christ Church, Oxford 1

2 Overview 1. Gen Reactor technology: RBMK 3. Reactor technology: VVER 4. Which reactor is good then??? 2

3 For those who have not seen this graph yet :-) 3

4 2. Reactor technology RBMK Former USSR: Lithuania, Ukraine, Russia = LWGR (graphite moderated, light water cooled) VVER Former USSR + Czech R., Slovakia, Hungary, Bulgaria, Finland, East Germany, India, China, Iran, Turkey = PWR (pressurised water reactor) 4

5 RBMK = containment? + void? Graphite moderator Light water coolant Boiling in channels Low enrichment Variable Pu vector 5

6 6

7 RBMK nuclear island from above... 7

8 RBMK core: 11m x 7m high 8

9 Reactor hall 9

10 Mk 1 10

11 Mk 2 11

12 RBMK Mk 2 12

13 RBMK Key technical characteristics Core parameters Power, MW: Electric Thermal RBMK1000 RBMK Number of fuel channels, pcs. Coolant Steam characteristics before the turbine: pressure, MPa Temperature, С Steamwater mixture Steamwater mixture 6, , at the core outlet Water flow through the reactor, t/h 270 RBMK-1000 RBMK-1500 Max. power of the fuel channel with fuel assembly, MW 3 4,25 Service time, years 7 6 FA dimensions: length, mm diameter, mm FA weight, kg Coolant temperature: - at the core inlet FA characteristics U-235 enrichment depending on design modification,% 2,6; 2,8 2,4; 2,6 Average fuel burn-up depending on enrichment, MW d/kg U 25,8 (2,6%) 30 (2,8%) 20,5 (2,4%) 26 (2,6%) Max. fuel burn-up depending on enrichment, MW d/kg U 29,6 (2,6%) 34,5 (2,8%) 23,5 (2,4%) 30 (2,6%)

14 RBMK 1500 IGNALINA 14

15 RBMK 1500 IGNALINA More of this nice accent on: 15

16 Now only 1 RBMK being built

17 Many changes: may RBMK return? CURRENTLY: Higher enrichment Erbium burnable poison Void coefficient negative now New control rods PROPOSAL: containment 17

18 CONTAINMENTs D.I.Y.

19 3. VVER (WWER) reactors Thermal nuclear reactors Pressurised Light Water used as moderator Pressurised Light Water used as coolant Steam generator used to produce steam 19

20 Remember: PWR in the world USA Submarine Russian Submarine SSN-571Nautilus PWR = submarine technology NPP Shippingport-1 NPP Novovoroněž-1 68 MWe 210 MWe 20

21 Remember where the PWR comes from 21

22 VVER reactor history First demoplants: PWR at Shippingport in USA: 1957 VVER-210 at USSR: 1964 In USSR focused on RBMK reactors (LWGR) at that time, eastern PWR development initially in Eastern Germany!! 7 year technology gap 22

23 MOTTO: Build and ship around 23

24 VVER reactor history Railroads were the limiting factor => slender&high R.P.V. => small core => higher enrichment Horizontal steam generators => large volume => initially no containment/confinement Faster development in fewer steps => robust and conservative approach 24

25 VVER typical features Core: triangular lattice => hexagonal fuel assemblies fuel assembly with grid 12.6mm small core size => higher enrichment Small RPV diameter => neutron damage on RPV (156 mm water for VVER440 (V-230), 263 mm for VVER1000 (V-320) between fuel and RPV) => high RPV (esp. for VVER440) Primary circuit: more loops (6 for VVER440)=>more water horizontal steam generators=>less sediments Safety: VVER440 (V-230): LOCA: 32mm diameter, weak ECCS From VVER440(V-213): LOCA: full rupture, standard ECCS 25

26 VVER typical features VVER 440: very efficient control rods -different design than in other PWR - effort of being robust and simple - large worth, quick scram -resulting in a long RPV which also means a lot of water -unusual burnout of fuel attached to the control rod -safety studies: control rod ejection is more dramatic than PWR VVER 1000: standard approach to control rods, like PWR 26

27 Before I show you the reactors... Q U I Z time! a/ VVER b/ BWR c/ RBMK d/ CANDU e/ PWR

28 VVER Courtesy of Skoda-JS

29 NPP VVER 440 (V 230) 29

30 VVER 440 V

31 NPP VVER 440 (V 213) 31

32 VVER 440, reactor hall cross section 32

33 VVER 440 primary circuit 33 Courtesy of Skoda-JS

34 VVER 440 steam generator 34 Courtesy of Skoda-JS

35 VVER 440 RPV cross section in 2 levels 35 Courtesy of Skoda-JS

36 VVER 440 fuel pin and fuel assembly 36

37 VVER 440 Dukovany, Loviisa 37

38 VVER 440 x VVER 1000 comparison 2 x x 440 Reactor type VVER 440 (V 213) VVER 1000 (V320) Thermal power 1375 MW 3000 MW RPV diameter 3.56 m 4.5 m RPV height 11.8 m 10.9 m # of fuel assemblies Fuel load t t Moderator/coolant H2O H2O RPV pressure MPa 15.7 MPa Coolant temperature 267 C C 290 C C 38

39 VVER 1000 V Courtesy of Skoda-JS

40 VVER 1000 reactor: Main parts: 40

41 Mix: VVER Western technology NPP Temelín NPP Busehr 41 Courtesy of Skoda-JS

42 Currently building: AES-92 = VVER1000 V392 (Belene) Primary circuit: Number of loops Coolant pressure MPa Core inlet temperature 291 C Core outlet temperature 321 C FA number 163 # of control rods 121 Maximum FA burn-up >60 MWd/kgU 42

43 Currently building AES-2006 ~ VVER1200 ~ V491 (now also known as MIR-1200) Primary circuit: Number of loops 4 Coolant pressure 16.2 MPa Core inlet temperature 299 C Core outlet temperature 330 C FA number 163 # of control rods 121 Maximum FA burn-up <70 MWd/kgU 43

44 All can be seen at the cradle of VVER reactors NOVOVORONEZH

45 Planned: VVER640 (V407) Primary circuit: Number of loops 4 Coolant pressure Core inlet temperature 15.7 Mpa Core outlet temperature Thermal power Enrichment Average FA burnup 294 C 322 C 1800 MW 3.6% 45MWd/kgU 45

46 Planned: VVER1500 Primary circuit: Number of loops 4 Coolant pressure Core inlet temperature 15.7 Mpa Core outlet temperature Thermal power Enrichment Average FA burnup 299 C 330 C 4250 MW 4.4% 45-55MWd/kgU 46

47 Newest VVER type currently offered: VVER-1200 a.k.a. MIR-1200 a.k.a. V-491 a.k.a. AES Courtesy of Skoda-JS 47

48 VVER reactor specification VVER are PWR reactors, the physics is the same VVER440 robust approach VVER1000 very close to western PWR, with specific pros&cons Several dozens of units operational, many in construction phase, good operating record 48

49 4. Which reactor is good / bad? Several PERFORMANCE indicators: Availibility factor Load factor Capacity factor Operating factor... Also: SAFETY + SECURITY indicators (WANO/INPO lectures to come) 49

50 IAEA website helps too! VVER440 50

51 IAEA website helps... VVER

52 Comparison of 4 LWRs: Gen III Courtesy of J. Misak: NRI Rez

53 Comparison of 4 PWRs: Gen III Courtesy of J. Misak: NRI Rez

54 THANK YOU (15 BACK UP SLIDES READY AND ENCLOSED WITH DATA FOR EAGER READERS...) 54

55 Comparison of 4 PWRs: Gen III Courtesy of J. Misak: NRI Rez

56 VVER performance 56 Courtesy of D. Gilchrist, ENEL

57 VVER reactor history: Voronezh types PROTOTYPES Power/ MWe Place Start Decommissioned VVER Novovoronezh VVER Rheinsberg VVER Novovoronezh

58 VVER reactor history: Voronezh types VVER 440 (i.e. rated 440MWe) 1st generation Feature Place Start V 170 Novovoronezh 1972 V 230 Kola 1973 Armenia 1980 V 270 seismic VVER for export, RBMK for home: 17 VVER440 units built, 13 out of Russia 58

59 VVER reactor history: Voronezh types VVER 440 2nd generation (i.e. project after`70) Feature Place Commissioned Kola 1982 V 213 Ice + containment Loviisa 1977 V 213 condenser Dukovany 1985 V 213 Again for export: 18 units built, 16 out of Russia 59

60 VVER reactor history: Voronezh types VVER 1000 (i.e. power 1000MWe) 2nd generation Place Commissioned V 178 Novovoronezh 1981 V 302 Nikolajev 1983 V 338 Kalinin 1985 V 320 Balakovo 1986 More than 20 units built, other still in construction.. 60

61 VVER reactor history: Voronezh types 3rd + 4th generation (i.e. outlook) From the `80-ies many variants of VVER planned: V318 (440MWe) V428(1000MWe), V407(640MWe), V392(1000MWe) in different stages of planning and construction 61

62 VVER 1000 comparison design parameters V-320 V-320 Temelín V-428 V Average burn out, MWd/kgU Enrichment, % Profiled fuel no yes?? Planned lifetime, years LBB (Leak Before Break) no yes yes yes Probability of core melting 10Е-5 10Е-5 10Е-5 10Е-6 no yes yes yes 3х100% 3х100% 4х100% 4х100% Double containment no no yes yes Core catcher no no yes yes Thermal Power, MW Fuel cycle, years Annual load factor, hours ATWS ECCS concept 62

63 VVER 1000 comparison design parameters V-320 V-320 V-428 V-466 Temelín Primary circuit Pressure, MPa 15,7 15,7 15,7 15,7 Outlet temperature, [ C] (321)* 320 (321)* Inlet temperature, [ C] 289,7 289,7 289,7 (291)* 289,7 (291)* Flow, [m3/h] RPV inner diameter, [mm] RPV thickness at the core level, [mm] 192,5 192,5 192,5 195 RPV - height, [mm]

64 NPP Loviisa VVER

65 Loviisa

66 VVER 440 V

67 AES-92: BELENE

68 LWR positive/negative void 68

69 Void coefficient... in my reactor 69