Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions

Transcription

1 ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM VVER-100 Reactor Plant and Safety Systems Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions N.S. Fil Chief Specialist, OKB GIDROPRESS April -3, 01 Johannesburg, Sandton Convention Center

2 Gidropress is the chief designer of VVER nuclear steam supply system Role of Gidropress in Rosatom s Key Activities Fuel fabrication Mining Research and development Conversion and enrichment NPPs engineering & construction Power equipment and services Gas centrifuges manufacturing Spent nuclear fuel treatment Power Generation Gidropress The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated

3 INTRODUCTION The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 3

4 VVER-100 designer OKB GIDROPRESS has been established in 1946 to develop designs of nuclear steam supply systems (NSSS) and separate equipment for nuclear installations. Some milestones: 194 Research heavy water reactor 1954 Steam generator for 1st NPP 1963 Lead-bismuth NSSS for submarine First VVER Boiling water reactor VK Fast sodium reactor BOR First VVER First VVER-1000 Now over 50 VVER-440 and VVER-1000 are in operation in Russia, Ukraine, Armenia, Finland, Bulgaria, Hungary, Czech Rep., Slovakia, China, Iran. New VVER Gen III+ of MWe, Gen IV VVER-SCP and lead-bismuth SVBR-100 are under development. The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 4

5 VVER evolution VVER: Vodo-Vodianoy Energeticheskiy Reactor -Pressurized light water reactor -Loop-type reactor coolant system -Reactor nozzles at elevations -No RPV penetration below inlet nozzles -Horizontal steam generators -Hexagonal fuel assemblies About 1500 reactor-years of operating time The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 5

6 VVER evolution 1 upper unit, pressure grid, 3 core barrel, 4 basket, 5 vessel, 6 shield, working assembly, compensating assembly VVER-1 of 60 MWth (Novovoronezh NPP unit 1, 1966) Now VVER-100 is the main design for near term nuclear power program in Russia and for bidding abroad The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 6

7 VVER-100 DESIGN BASES The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated

8 Reference plants IAEA standard Safety of Nuclear Power Plants: Design (SSG-/1, Feb 01) Item 4.14 Items important to safety for a nuclear power plant preferably shall be of a design that has previously been proven in equivalent applications, and if not shall be items of high quality and of a technology that has been qualified and tested. VVER-100 is the evolution of operating VVER-1000 by improving plant performance and increasing plant safety. Plant performance Rated power 300 (3000) MWth Primary pressure 16. (15.) MPa Secondary pressure.0 (6.3) MPa Coolant temperature 39 (30) C Plant safety Passive decay heat removal system Passive containment cooling system Passive hydrogen removal system Passive corium catcher The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated

9 Reference plants Operating VVER-1000s VVER-1000 reactor plant for AES-91(Tianwan NPP) VVER-1000 reactor plant for AES-9 (Kudankulam NPP) Technical Assignment for VVER-100 reactor plant design: To proceed from AES-91 and AES-9, to meet Russian norms, IAEA, EUR, WENRA to meet BIS requirement VVER-100 reactor plant EUR organization has certified in 00 that AES-9 design has passed all the steps of the analysis of compliance vs. EUR. Following this analysis, a specific subset of the EUR volume 3 dedicated to AES-9 project has been published by EUR organization. The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 9

10 Reference plants The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 10

11 Plant states Plant states as per SSR-/1 Item 5.1 Plant states considered in VVER-100 design DBC-1 DBC- DBC-3 DBC-4 Complex Severe Normal Operation Incidents Sequences Accidents Operational States Design Basis Conditions (DBC) Design Basis Accidents Design Extension Conditions The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 11

12 Design extension conditions SSR-/1 Item 5. The design extension conditions shall be used to define the design basis for safety features and for the design of all other items important to safety that are necessary for preventing such conditions from arising; or, if they do arise, for controlling them and mitigating their consequences. The relevant technical provisions (both active and passive) are implemented in VVER-100 design to meet the acceptance criteria established for design extension conditions. These provisions ensure back-up for all safety functions needed to prevent the progression of beyond design basis accidents to Fukushima-like scenarios. The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 1

13 VVER-100 DESIGN FEATURES The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 13

14 RCS design Reactor 1 In-core detectors Top head unit 3 Protective tube unit 4 Core barrel 5 Core baffle 6 Core Reactor pressure vessel Safety class 1 Seismic category 1 Design parameters 1.6/350 No welds in core region No joints below cold leg The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 14

15 RCS design HT surface m; number of HT tubes 16x1.5 mm Safety class - 1, Seismic category 1. Primary collector: Safety class - 1 Seismic category 1 Height 5.1 m Max. diameter - 1. m Max. wall thickness 0.1 m Steam generator The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 15

16 RCS design Pressurizer Safety class 1 Seismic category -1 Volume 0 m3 Design parameters 1.6/350 Heaters Power -.5 МW Safety class Relief tank Volume 30 m3 Internal diameter m Length.5 m Design parameters 0.6/ The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 16

17 RCS design Main coolant pump Head 0.59 Mpa Flow rate 1500 m 3 /h Speed 1000/50 rot/min Current 50 Hz Massive flywheel ensures smooth reduction of flow rate in case of loss of power. The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 1

18 Reactor core Core FA Top nozzle Spacer grid Fuel rods 163 fuel assemblies of to 5% enrichment. To 11 control rods. Bottom nozzle 31 fuel rods. 1 guide channels. 13 spacer grids. The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 1

19 Fuel assembly FA of V-1 TVS MTVS UTVS TVS- TVS-M TVS-006 Top nozzle (fixed) Top nozzle (removable, enlarged stroke of spring unit) Top nozzle (removable, enlarged stroke of spring unit) Top nozzle (removable, enlarged stroke of spring unit, increased rigidity due to closed shell, modification with improved thermal control) Top nozzle (removable, enlarged stroke of spring unit, increased rigidity due to closed shell, version with improved thermal control) Top nozzle (removable, enlarged stroke of spring unit, increased rigidity due to closed shell, version with improved thermal control) Bundle (steel skeleton) Bottom nozzle Bundle (steel skeleton) Lower grid (expanded thickness, rigid attachment on the whole perimeter, splinted FEs) Bottom nozzle (light-weight) Bundle (zirconium skeleton, uranium - gadalinium fuel) Lower grid (enlarged thickness, rigid attachment on the whole perimeter) Bottom nozzle (light-weight) Bundle (zirconium rigid skeleton, 1/15 CSGs of increased height and cell with 0,3 mm wall thickness, Э635 alloy channels) Lower grid (increased thickness, rigid attachment on the whole perimeter) Bottom nozzle (light-weight) Bundle (zirconium rigid skeleton, CSG of increased height and cell with 0,3 mm wall thickness, Э635 alloy channels, CSG is optimized up to 13 pc., fuel column height is increased to 150 mm) Lower grid (increased thickness, rigid attachment on the whole parameter, collet securing of FEs/U-Gd FEs) Bottom nozzle (light-weight, short-cut, antidebris filter) Bundle (zirconium rigid skeleton, CSG of increased height and cell with 0,3 mm wall thickness, Э635 alloy channels, CSG is optimized up to 13 pc., fuel column height is increased to 150 mm) Lower grid (increased thickness, rigid attachment on the whole parameter, collet securing of FEs/U-Gd FEs) Bottom nozzle (light-weight, short-cut, antidebris filter) Proven FA design: from VVER-1000 to VVER The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 19

20 VVER-100 SAFETY SYSTEMS The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 0

21 Reactivity control Reactivity control means in VVER-100 Inherent core nuclear feedbacks (reactivity effects and coefficients) provide compensation of rapid reactivity changes and limit reactor power increase. Reactivity coefficients (and effects) for VVER reactors are as follows: by coolant temperature and density, by fuel temperature, by reactor power and by boron acid concentration in the coolant. Two independent control systems (ability to independently bring the reactor to subcritical state): Cluster system Boron control + Reactivity compensation by burnable poison in the fuel pellet The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 1

22 Reactivity control Control rod grouping - groups 1 9 are for control and protection - groups 1 are for protection only B4C 9 - номер ТВС - номер группы ОР DyO3TiO TiO The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated

23 Overpressure protection Emergency gas removal system The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 3

24 Emergency core cooling Passive ECCS Passive part of emergency core cooling system is intended for boric acid solution supply into the reactor at the primary pressure less than 5,9 MPa under LOCA till start of active ECCS. HA HA HA HA Parameters Value P Nominal pressure, MPa 5,9 C Н 3 ВО 3 concentration, g/kg 16 V Accumulator/solution volume, m 3 60 / 50 The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 4

25 Thank You for Attention! Nikolay Fil Chief Specialist OKB GIDROPRESS XXX Phone: XXX The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn t lead to any obligations to Rosatom and its affiliated 5