Advanced Designs of VVER Reactor Plant
V.A. Mokhov
VVER-2010. Experience & Perspectives 01-03 November 2010. Prague. Czech Republic INTRODUCTION
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).
2 INTRODUCTION
Current challenges
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.
3 INTRODUCTION
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.
4 EVOLUTION OF VVER
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.
5 EVOLUTION OF VVER First designs of low and medium power (1955 – 1975) RP design RP type Site (units) Status RP generation VVER-1 VVER-210 NVNPP (1) DCOM 1 VVER-2 VVER-70 NPP «Rheinesberg» (1) DCOM 1 VVER-3М VVER-365 NVNPP (2) DCOM 1 V-179 VVER-440 NVNPP (3,4) SLE 1 V-230 VVER-440 Kola NPP (1,2), SLE 1 NPP «Kozloduy» (1-4), NPP «Nord» DCOM (1-4), NPP «Bohunice» (1,2) V-270 VVER-440 Armenian NPP UO 1 V-213 VVER-440 Kola NPP (3,4), Rovno NPP (1,2), UO 2 NPP «Loviisa» (1,2), NPP «Paks» (1- 4), NPP «Bohunice» (3,4), NPP «Mochovce» (1,2), NPP «Dukovany» (1-4), NPP «Nord» (5) DCOM
6 EVOLUTION OF VVER Designs of high-power (1966 – 2003) RP RP type Site (units) Status RP design generation V-187 VVER-1000 NVNPP (5) SLE 2 V-302 VVER-1000 South Ukraine NPP (1) UO 2 V-338 VVER-1000 South Ukraine NPP (2), Kalinin NPP UO 2 (1,2) V-320 VVER-1000 Balakovo NPP (1-4), Zaporozhe NPP UO 2 (1-6), Rovno NPP (3,4), Khmelnitsk NPP (1,2), South Ukraine NPP (3), Rostov NPP (1,2), NPP «Temelin» (1,2), Kalinin NPP (3), NPP «Kozloduy» (5,6) V-392 VVER-1000 *) D 3 V-446 VVER-1000 NPP «Bushehr» (1) COM 3
7 EVOLUTION OF VVER
Modern designs (2000 – 2007)
RP RP type Site (units) Status RP design generation V-392B VVER-1000 Balakovo NPP (5) D 3 V-412 VVER-1000 NPP «Kudankulam» (1,2) UC 3 V-428 VVER-1000 Tianwan NPP (1,2) UO 3 V-407 VVER-640 - D 3+ V-466B VVER-1000 NPP «Belene» (1,2) D 3+ V-392М VVER-1200 NVNPP-2 (1,2) UC 3+ V-491 VVER-1200 LNPP-2 (1-4), UC 3+ BaltNPP (1,2) D V-448 VVER-1500 - D 3+
8 EVOLUTION OF VVER
Advanced and innovative designs
RP RP type Site (units) Status RP design generation V-498 VVER-600 - CtP 3+ V-501 VVER-1200А - CtP 3+ VVER-1800 - CtP 3+ V-393 VVER-SCP - CtP 4
Abbreviations used: SLE – service life extended; COM – commissioning; CtP – concept proposal; D – design is developed; DCOM – decommissioned; UC – NPP under construction; UO – under operation. 9 EVOLUTION OF VVER
Modern NPPs with VVER-1000 reactor plant
India Iran “Kudankulam” NPP “Bushehr” NPP
China “Tianwan” NPP
10 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.
11 VVER-1200 for AES-2006
References of design
AES-91 with V-428 ("Tianwan“ NPP)
LNPP-2 with V-491
MIR-1200
Development of design RP V-491 for LNPP-2 was started in 2007.
12 VVER-1200 for AES-2006
Main parameters of reactor plant
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, оС 290 298,6 Coolant temperature at the reactor outlet, оС 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 49 до 70 equilibrium fuel cycle), MWD/kgU Refueling period, month 12 12/(18-24) Time of fuel residence in the core, year 4 4/5 13 VVER-1200 for AES-2006
Vessel
Parameter Value VVER- VVER- 1200 1000 (V-428) Length , mm 11185 11185
Inner diameter, mm 4250 4150
Wall thickness in the 197,5 192,5 beltline region, mm
Mass, t 323 317 14 VVER-1200 for AES-2006
Steam generator
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.
15 VVER-1200 for AES-2006
Fuel improvement Advanced fuel assemblies TVS-2 TVS-2М TVS-2006 Cap Short cap Design of FA Cap main (Shell of increased components rigidity, enhanced thermal control) (spacing grid, skeleton, cap,
tail-piece, fuel
100 100 45 45 rod) is unified on the basis of
Bundle solutions proved
0 мм мм 0 0
5 5 50 50 (zirconium rigid by successful
skeleton, 95 мм 95
Bundle мм 95 100 100 zirconium spacing long-term (zirconium rigid grid of increased operational skeleton, height, cell wall
Bundle zirconium spaсing experience 50 50 thickness 0,3 mm,
(zirconium rigid grid of increased channels of alloy 0 мм 0
0 мм 0 height, cell wall 5 skeleton, 5 E635, optimized number zirconium spaсing thickness 0,3 mm, of zirconium spacing grids, grid of increased channels of alloy fuel stack height is height, cell wall E635, optimized number increased by 200 mm) thickness 0,3 mm, of zirconium spaсing grids, channels of alloy fuel stack height is E635) increased by 150 mm) Lowel grid (fastening Lower grid Lowel grid (collet of fuel rods/gadolinium fastening of fuel rods/ fuel rods with axial
gadolinium fuel rods) clearance)
00 мм мм 00 00
1 1 100
100 Short tail-piece 100 Tail-piece 100 Tail-piece
706 / 494,5 738 / 527,3 750 / 534,1 FA/fuel mass, kg-f 16 VVER-1200 for AES-2006
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.
17 VVER-1200 for AES-2006
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
18 VVER-1200 for AES-2006
NPP safety (continued) . 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.
19 MIR-1200
Consortium participants 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.
20 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.)
21 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.
22 MIR-1200
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; . Commissioning work; . Services for the Units under operation.
23 VVER-600
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. 24 VVER-600
Main equipment layout
25 VVER-600
Main equipment layout (cont.)
Spent fuel pool RCP set Reactor
Steam generator
ECCS accumulator-1
Pressurizer
26 Ø 36 m VVER-600
Main equipment layout (cont.)
Passive heat removal system
Pressurizer
2nd stage HA
Steam generator ECCS HA
Main coolant pipeline
Reactor 27 VVER-600 SR (Generation 3++)
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
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)
28 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.
29 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 30 VVER-SCP (Generation 4) Main parameters of fuel assembly: Parameter Value 1 Width across flats, mm 205 Quantity of fuel rods in FA, pcs. 252 Fuel rod diameter and cladding 2 10.7 0.55 thickness, mm
Fuel pellet diameter, mm 9.4 3
Pitch of fuel rod triangular grid, mm 12 4 Quantity of guiding tubes for RCCA, 18 pcs. Central tube, pcs. 1 Diameter and thickness of guiding 12 0.55 and central tubes, mm Jacket thickness, mm 2.25 31
5 CONCLUSION
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
32 Thank you for your attention!
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