Yu.М. Аshurko 1), E.E. Marinenko 1), М.V. Bakanov 2), Yu.V. Nosov 2), O.A. Potapov 2), Yu.M. Krasheninnikov 3)

Transcription

1 Yu.М. Аshurko 1), E.E. Marinenko 1), М.V. Bakanov 2), Yu.V. Nosov 2), O.A. Potapov 2), Yu.M. Krasheninnikov 3) 1) State Scientific Center of the Russian Federation Institute for Physics and Power Engineering (SSC RF-IPPE), Оbninsk, 2) Beloyarsk NPP (BelNPP), Zarechny 3) State Scientific Center Research Institute of Atomic Reactors (SSC RIAR), Dimitrovgrad Submitted to the 47 th Meeting of the IAEA Technical Working Group on Fast Reactors, International Atomic Energy Agency, Vienna, Austria, May 19-23, 2014

2 IAEA HQ, Vienna, Austria, May 19-23, PART 1. GENERAL INFORMATION ON RUSSIAN NPPs AND PROGRAM FOR FAST REACTOR DEVELOPMENT

3 IAEA HQ, Vienna, Austria, May 19-23, GENERAL INFORMATION ON NPPs IN RUSSIA In 2013, there were 33 nuclear power units in operation at 10 NPPs in Russia They produced about 16% of the Russia s total electricity generation in 2013 Total electric power capacity of all Russian NPPs equals to 25.2 GWe Over 15 power units are currently under construction In 2013, the Russian NPPs produced billion kw h in total In 2013, load factor of the Russian NPPs reached 77.88% 39 events of abnormal operating conditions of the NPPs that occur in 2013 can be classified according to the INES scale as follows: 11 events below INES scale, i.e. out of scale cases 27 events at level "0 1 event at level "1"

4 LIST OF NPP POWER UNITS OPERATING IN RUSSIA (1/2) No Power unit Reactor type Year of commissioning Operating power units Installed electric power, MW e 1 Novovoronezh-3 VVER Novovoronezh-4 VVER Kola-1 VVER Leningrad-1 RBMK Kola-2 VVER Bilibino-1 EGP Bilibino-2 EGP Bilibino-3 EGP Leningrad-2 RBMK Bilibino-4 EGP Kursk-1 RBMK Kursk-2 RBMK Leningrad-3 RBMK Beloyarsk-3 BN Novovoronezh-5 VVER Leningrad-4 RBMK Коla-3 VVER IAEA HQ, Vienna, Austria, May 19-23,

5 LIST OF NPP POWER UNITS OPERATING IN RUSSIA (2/2) No Power unit Reactor type Year of commissioning Installed electric power, MW e Operating power units 18 Smolensk-1 RBMK Kursk-3 RBMK Kola-4 VVER Kalinin-1 VVER Kursk-4 RBMK Smolensk-2 RBMK Balakovo-1 VVER Kalinin-2 VVER Balakovo-2 VVER Balakovo-3 VVER Smolensk-3 RBMK Balakovo-4 VVER Rostov-1 VVER Kalinin-3 VVER Rostov-2 VVER Kalinin-4 VVER Total IAEA HQ, Vienna, Austria, May 19-23,

6 FAST REACTORS Russia has 2 fast reactors in operation: Test reactor BOR-60 at the SSC RF RIAR (Dimitrovgrad) Commercial power unit No. 3 of the Beloyarsk NPP (BelNPP) with sodium cooled fast reactor BN-600 (Zarechny) Research reactor BR-10 at the SSC RF IPPE (Obninsk) is being prepared for decommissioning No. 4 power unit of the Beloyarsk NPP with sodium cooled fast reactor BN-800 is under construction IAEA HQ, Vienna, Austria, May 19-23,

7 IAEA HQ, Vienna, Austria, May 19-23, PROSPECTIVE ACTIVITIES ON SFR IN RUSSIA (1/2) In accordance with the FTP Nuclear power technologies of new generation for the period of and with outlook to 2020, the R&D on advanced sodium cooled fast reactors (SFR) and fast reactors with heavy liquid metal coolant (HLMC) is underway. Sodium cooled fast reactors: Development of the large-scale sodium fast reactor BN-1200 design and R&D implementation for its substantiation Designing and construction of the research sodium-cooled fast reactor MBIR Design development and construction of the pilot plant for manufacturing MOX-fuel for BN-800 Upgrading of experimental facilities for justification of the SFR, including the BFS test facilities Fast reactors with HLMC: Design development of SVBR-100 reactor facility with lead-bismuth coolant (LBC) and carrying out R&D required for its substantiation, construction of SVBR-100 prototype facility Implementation of R&D on justification of the design of the NPP with lead cooled reactor BREST-ОD-300 with appropriate revision of the design, construction of a pilot plant with BREST reactor

8 PROSPECTIVE ACTIVITIES ON SFR IN RUSSIA (2/2) The following activities are also specified in the Federal Targeted Program Development of new-generation integrated systems of codes for safety analysis and substantiation of advanced nuclear power plants and nuclear fuel cycle Development of dense fuel fabrication technologies for fast reactors Development of advanced structural materials Development of closed nuclear fuel cycle technologies IAEA HQ, Vienna, Austria, May 19-23,

9 IAEA HQ, Vienna, Austria, May 19-23, PART 2. PROJECTS AND ACTIVITIES RELATED TO FAST REACTORS IN RUSSIA

10 FAST REACTORS Russia has 2 fast reactors in operation: Test reactor BOR-60 at the SSC RF RIAR (Dimitrovgrad) Commercial power unit No. 3 of the Beloyarsk NPP (BelNPP) with sodium cooled fast reactor BN-600 (Zarechny) Research reactor BR-10 at the SSC RF IPPE (Obninsk) is being prepared for decommissioning No. 4 power unit of the Beloyarsk NPP with sodium cooled fast reactor BN-800 is under construction IAEA HQ, Vienna, Austria, May 19-23,

11 NPP WITH THE BN-600 REACTOR BASIC OPERATIONAL PARAMETERS On April 8, 2014, power unit No.3 of the Beloyarsk NPP with sodiumcooled fast reactor BN-600 celebrated the 34th anniversary since it was connected to the grid The rated electric power 600 MW was reached in December 1981 BN-600 power unit has produced about 129 billion kw h of electricity during the operation period In 2013, BN-600 power unit: was in operation on the power levels during 7398 hours produced million kw h of electricity delivered Tcal of heat to heat consumers from power unit collectors had load factor equal to 78.39% The average load factor for the period of commercial operation since 1982 to 2013 equaled to 74.4%. In 2013, there were no unscheduled shutdowns of the power unit Three power decreases occurred during 2013 All these events are classified in accordance with INES scale as out of scale cases There were 2 scheduled power unit shutdowns for refueling and preventive maintenance works (PMW) in 2013: Spring PMW from to Autumn PMW from to IAEA HQ, Vienna, Austria, May 19-23,

12 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-600 REACTOR BN-600 power unit basic parameters Parameter Value Thermal power, MW 1470 Electric power, MW 600 Number of heat removal loops 3 Primary circuit configuration Pool Steam generator design Once-through, sectional-modular Maximum neutron flux density, n cm -2 s Fuel UO 2 Max. fuel burn-up, % h. a Inlet/outlet core coolant temperature, ºС 377/550 Inlet/outlet SG coolant temperature, ºС 518/328 Inlet/outlet SG water/steam temperature, ºС 241/507 Live steam pressure, MPa 13.2 Design lifetime, year 30

13 NPP WITH BN-600 REACTOR LOAD MAP OF BN-600 POWER UNIT IN 2013 Power, MW 1 - decrease of the unit power down to 75-81% of nominal power due to increased radiation rate under the reactor dome (from to ) 2 - scheduled shutdown of the power unit for medium repair (from to ) 3 reactor operated at 98 99,5% N nom (from to ) due to increased coolant temperature at the experimental subassembly outlet 4 - decrease of the unit power to 33% due to loop switch-off ( ) 5 - scheduled shutdown of the power unit for routine repair (from to ) Data (month, year) IAEA HQ, Vienna, Austria, May 19-23,

14 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-600 REACTOR BASIC REPAIR AND MAINTENANCE WORKS IN 2013 Reactor refueling Medium repair of the primary and secondary main circulation pumps Routine control of structural materials of the primary circuit auxiliary equipment and piping Pneumatic testing of the reactor vessel, guard vessel, equipment and piping of the reactor facility Restoration of biological shield (replacement of leaking plug) Operational chemical cleaning of the evaporators in SG-6 Repair of equipment and piping of the secondary and tertiary circuits of SG-4, 5,6 Repair of equipment and piping of the tertiary circuits of TG-4, 5, 6 Medium repair of TG-4 Routine repair of TG-5 and 6 Routine repair of G- 4, 5, 6 Replacement of emergency feed pumps and condensate pumps

15 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-600 REACTOR ACTIVITIES ON DESIGN LIFETIME EXTENSION On April 7, 2010, the Beloyarsk NPP received the Rostechnadzor s license for lifetime extension of BN-600 power unit until March 31, 2020 In 2013, a range of activities were carried out within the Program on design lifetime extension: Investigation and substantiation of remaining operation life of the power unit systems and components Replacement of the power unit equipment and systems with lifetime expired It has been officially decided to complete the investment project "Design Lifetime Extension of Power Unit No.3 of the Beloyarsk NPP" All the tasks on ensuring compliance with the license for power unit No. 3 operation in the additional period, assessment and substantiation of further operation of the power unit components, acquisition and replacement of the wornout equipment have been fully completed. This project is over.

16 EXPERIMENTAL REACTOR BOR-60 BOR-60 reactor is used for: Study of advanced nuclear fuels Testing of new structural materials and coolants Isotopes production Tests of various equipment of fast reactors Heat and electricity production BOR-60 reactor facility has been in operation for over 44 years In December 2009, Rostechnadzor issued a license to the RIAR for further operation of BOR-60 reactor facility until IAEA HQ, Vienna, Austria, May 19-23,

17 IAEA HQ, Vienna, Austria, May 19-23, BOR-60 REACTOR BASIC PARAMETERS Parameter Value Thermal reactor power, MW 60 Electric power, MW 12 Maximum neutron flux density, n cm -2 s Maximum core power density, kw/l 1100 Average core neutron energy, MeV 0.45 BOR-60 reactor longitudinal section Fuel UO 2, UO 2 -PuO 2 Fuel burn-up rate, %/year up to 6 Neutron fluence per year, n cm Damage dose rate, dpa/year up to 25 Inlet coolant temperature, ºС Outlet coolant temperature, ºС up to 530 Core run duration, days up to 120 Reactor availability up to ~0.73 Number of cells: 265 for FSAs 156 for absorber rods 7 instrumented cells 3

18 EXPERIMENTAL REACTOR BOR-60 BOR-60 BASIC OPERATIONAL PARAMETERS IN 2013 Index Value Time of reactor operation on power exceeding minimum controlled level, h 5058 Reactor load factor 0.58 Max reactor power, MW 53 Energy output: heat, MW h electricity, MW h Time of SG operation: SG-1, h SG-2, h Heat delivery to consumers, Gcal In 2013, there were 9 reactor shutdowns: 1 unscheduled shutdown and 8 scheduled ones for preventive maintenance work, partial refueling, loading and unloading of experimental devices and assemblies One unscheduled shutdown was carried out by automatic initiation of reactor scram due to failure of the reactor control and protection system. INES level 0. IAEA HQ, Vienna, Austria, May 19-23,

19 Power, MW IAEA HQ, Vienna, Austria, May 19-23, EXPERIMENTAL REACTOR BOR-60 BOR-60 REACTOR OPERATION IN 2013

20 EXPERIMENTAL REACTOR BOR-60 EXPERIMENTAL WORKS CARRIED OUT IN 2013 Irradiation of assemblies with structural materials (zirconium alloys, structural materials of various reactor types) at temperatures from 320ºC to 450ºC Production of radioisotopes of strontium-89 and gadolinium-153 In-pile studies of capsules with dysprosium hafnate samples under temperatures from 500ºC to 600ºC In-pile tests of the SVBR-100 fuel pin models and fuel pin claddings from EP-823 steel, mock-up model of the stibium-beryllium neutron source for SVBR-100 reactor Irradiation of the models of absorbing elements of the BREST-OD-300 reactor based on boron carbide and hafnium dysprosium materials In-pile studies of fuel pin models with nitride fuel and cladding made of EP-823 steel In-pile studies of various steel samples for BREST reactor In-pile studies of fuel pin models with vibropacked MOX-fuel for MBIR reactor In-pile studies of various structural materials IAEA HQ, Vienna, Austria, May 19-23,

21 IAEA HQ, Vienna, Austria, May 19-23, EXPERIMENTAL REACTOR BOR-60 ACTIVITIES ON BOR-60 LIFETIME EXTENSION IN 2013 Technical inspection and lifetime extension of: Components of reactor control and protection systems and instrumentation Electrical equipment Replacement of: Uninterruptible power supply unit of emergency power supply system Reactor power monitoring devices Sodium level monitoring devices BOR-60 safety analysis report revised The substantiating documents required to obtain the Rostechnadzor s license for BOR-60 reactor operation after 2014 prepared

22 IAEA HQ, Vienna, Austria, May 19-23, EXPERIMENTAL REACTOR BR-10 CURRENT STATUS After about 44 years of operation, BR-10 experimental reactor was finally shutdown on December 6, 2002 and now it is in preparation for decommissioning Current status of BR-10 reactor is as follows: All FSAs unloaded from the core and replaced by the dummy subassemblies All FSAs placed into the interim storage Sodium drained from the primary and secondary circuits to the storage tanks and frozen The inner surfaces of the primary circuit cleaned from sodium and decontaminated Both loops of the secondary circuit cleaned from sodium Works on installation of facilities for coolant demercurization, conditioning radwaste of coolant and treatment of coolant are under way

23 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-800 REACTOR GENERAL INFORMATION Construction of the 4 th power unit with BN-800 reactor is carried at Beloyarsk NPP site Construction completion and power unit commissioning is scheduled for 2014 The reactor unit is at the stage of physical start-up BN-800 is planned to be used for: Closing fuel cycle and Recycling stocks of weapon-grade plutonium

24 IAEA HQ, Vienna, Austria, May 19-23, BN-800 main parameters Parameter Value Thermal power, MW 2100 Electric power, MW 880 Number of heat removal loops 3 Configuration of the primary circuit Pool Steam generator design Once-through, sectional-modular Maximum neutron flux density, n cm -2 s Fuel UO 2 -PuO 2 Max. fuel burn-up, % h. a. 9.9 Inlet/outlet core coolant temperature, ºС 354/547 Inlet/outlet SG coolant temperature, ºС 505/309 Inlet/outlet SG water/steam temperature, ºС 210/490 Live steam pressure, MPa 13.7 Design lifetime, year 40

25 CURRENT STATUS OF BN-800 CONSTRUCTION (1/2) Sodium coolant received The water-supply channel filled with water The main building vent stacks installed Two overhead power lines 220 kv connected to the substation "Kurchatov" and put into operation The main control room put into operation The diesel-generator facilities installed and tested The new fuel storage area put into operation. The controlled access area arranged The installation of the turbine unit started The central hall and turbine hall cranes installed The deaerator installed NPP WITH THE BN-800 REACTOR IAEA HQ, Vienna, Austria, May 19-23,

26 NPP WITH THE BN-800 REACTOR CURRENT STATUS OF BN-800 CONSTRUCTION (2/2) Two reserve auxiliary transformers put into operation The primary main circulation pumps installed and tested The dummy fuel subassemblies installed into the reactor. Comprehensive testing of the refueling system carried out The control rod drives set up and tested The reactor vessel tested, heated by gas and filled with sodium The primary sodium coolant is circulated by 2 main circulation pumps Installation of electric heating and thermal insulation of the secondary circuit equipment started Assembly of high-voltage electric equipment started The operating license for power unit No. 4 received IAEA HQ, Vienna, Austria, May 19-23,

27 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-800 REACTOR VIEWS OF BN-800 NPP SITE (1/6) Bird s-eye view of the reactor compartment (May 2013)

28 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-800 REACTOR VIEWS OF BN-800 NPP SITE (2/6) Bird s-eye view of the turbine hall and reactor compartment (May 2013)

29 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH THE BN-800 REACTOR VIEWS OF BN-800 NPP SITE (3/6) Power unit No. 4 (November 2013)

30 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-800 REACTOR VIEWS OF BN-800 NPP SITE (4/6) Assembly works in the reactor compartment (November 2013)

31 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH THE BN-800 REACTOR VIEWS OF BN-800 NPP SITE (5/6) The reactor compartment (December 2013)

32 IAEA HQ, Vienna, Austria, May 19-23, NPP WITH BN-800 REACTOR VIEWS OF BN-800 NPP SITE (6/6) The main control room (December 2013)

33 BN-1200 (1/2) BN-1200 is a new sodium-cooled fast reactor with improved technical and economic characteristics and enhanced safety for serial construction According to the FTP, design of the power unit with the sodium cooled fast reactor BN-1200 is currently under development The most important new conceptual technical and design decisions for the BN-1200 design are as follows: Pool type arrangement of the primary circuit with location of all sodium systems including cold traps and chemical-engineering control systems within the reactor vessel that makes it possible to eliminate any danger of radioactive sodium release outside the reactor vessel and catching fire Simplification of the refueling system due to elimination of intermediate storage drums of fresh and spent FSAs; organization of a capacious in-reactor vessel storage (IVS) of spent FSAs (SFSAs) to enable direct unloading of SFSAs (after their exposure in the IVS) from the IVS into washing cells and further into the exposure pool Transition from sectional-modular SG scheme to integral one based on application of straight-tube large-capacity modules Maximum enhancement of inherent safety features of the reactor facility and application of safety systems based on passive principles of functioning: passive systems of emergency protection, passive decay heat removal system via independent loops connected to the reactor vessel IAEA HQ, Vienna, Austria, May 19-23,

34 IAEA HQ, Vienna, Austria, May 19-23, BN-1200 (2/2) Besides, the BN-1200 design provides for: Traditional three-circuit design of the power unit Number of loops in the primary circuit - 4 (each loop contains one IHX and one MCP-1) Number of loops in the secondary circuit - 4 (each loop contains one IHX, one MCP-2 and one SG) Number of turbine units per power unit - 1 Steam reheating Operation of the NPP at the stable (mainly, rated) power level with load factor equal to at least 0.9 Flexible nuclear fuel cycle allowing transition from fuel made on the basis of plutonium extracted from SNF of thermal reactors to fuel made on the basis of own plutonium and providing opportunity for using different types of fuel (oxide, nitride) Construction of FOAK power unit with BN-1200 reactor at the BelNPP site is now under discussion

35 IAEA HQ, Vienna, Austria, May 19-23, BN-1200 MAIN PARAMETERS Parameter Value Rated thermal power, MW 2900 Electric power, MW 1220 Load factor, % 90 NPP efficiency, %: gross net Number of heat removal loops 4 Design lifetime of non-replaceable equipment, year 60 Primary circuit coolant flowrate, kg/s Secondary circuit coolant flowrate, kg/s Primary circuit coolant temperature (IHX outlet/inlet), С 410/550 Secondary circuit coolant temperature (SG outlet/inlet), С 355/527 Tertiary circuit parameters: live steam pressure, MPa live steam temperature, С feedwater temperature, С type of intermediate steam reheating Fuel Steam Nitride, MOX

36 IAEA HQ, Vienna, Austria, May 19-23, VIEW OF BN-1200 REACTOR VESSEL 1 IHX; 2, 3 main and guard vessels respectively 4 supporting structure 5 inlet plenum 6 core debris tray 7 core 8 pressure pipeline 9 MCP-1 10 refueling mechanism 11 CRDM 12 rotating plugs

37 IAEA HQ, Vienna, Austria, May 19-23, Multipurpose Research Sodium-Cooled Fast Reactor MBIR Development of the research fast reactor MBIR with sodium coolant is now at the detailed design stage The completion of the design activities and obtaining of the construction license are scheduled for 2014 Start-up of the MBIR is scheduled for 2019 at the SSC RIAR (Dimitrovgrad) Lay-out of the MBIR reactor vessel

38 IAEA HQ, Vienna, Austria, May 19-23, MBIR REACTOR BASIC CHARACTERISTICS Parameter Value Thermal power, MW ~150 Electric power, MW ~60 Maximum neutron flux density, n cm -2 s-1 ~ Standard fuel Vi-pack-MOX, (PuN+UN) Test fuel Innovative fuels, MA fuels and targets Core height, mm 550 Maximum linear rating of fuel element, W/cm 470 Maximum neutron fluence per year, n cm -2 ~ (up to 45 dpa) Design lifetime, year 50 Number of autonomous test loops with different coolants up to 5 (3 loop channels) Total number of experimental subassemblies and target devices for radioisotope production up to 14 (core) not limited (radial screen) Number of experimental channels up to 3 (core) Number of experimental horizontal channels (Ø 200 mm) up to 3 (outside reactor vessel) Number of experimental vertical channels (Ø 350 & 50 mm) up to 9 (outside reactor vessel)

39 PURPOSE OF THE MBIR REACTOR FACILITY Study of advanced nuclear fuel and absorber materials Tests of fuel in transient, cyclic and emergency modes of operation Study of closed fuel cycle, utilization of actinides and burning of long-lived fission products Irradiation of advanced structural materials Study of new and modified liquid-metal coolants, their quality monitoring and control facilities In-pile experiments for codes verification Tests and validation of new equipment types for different process systems, innovative control, monitoring and diagnostic instruments and systems Production of radioisotopes for a variety of applications Applied research using neutron beams Usage of neutron beams in medicine (neutron therapy) IAEA HQ, Vienna, Austria, May 19-23,

40 General view of BREST-OD-300 reactor BREST-OD-300 BREST is a lead cooled fast reactor with uranium plutonium mononitride fuel that uses a two-circuit heat transport system In accordance with the FTP, design of BREST-OD-300 lead-cooled fast reactor with on-site nuclear fuel cycle facilities is under development BREST-300 fast reactor and on-site fuel cycle facilities are to be built at the Siberian Chemical Plant near Tomsk IAEA HQ, Vienna, Austria, May 19-23,

41 IAEA HQ, Vienna, Austria, May 19-23, BREST-OD-300 BASIC PARAMETERS Parameter Value Thermal power, MW 700 Electric power, MW 300 Fuel Mixed nitride Primary circuit coolant Lead Coolant temperature (core inlet/outlet), C 420/540 Steam pressure (SG outlet), MPa 17.0 Feed-water temperature, C 340 Steam temperature (SG outlet), C 505 Number of fuel subassemblies 169 Fuel cycle, years 5 Maximum/Average fuel burn-up, % 9.0/5.5

42 SVBR-100 SVBR-100 Reactor module SVBR-100 is an innovative, small, modular fast reactor with lead bismuth coolant Joint Venture Open Stock Company "AKME-Engineering" established on a parity basis by the State Corporation "Rosatom" and En + Group (on the basis of Irkutskenergo Company) is involved in development and construction of the prototype facility with SVBR-100 reactor Reactor and power plant design are expected to be completed in 2014 Construction license is expected to be obtained in 2014 The prototype facility with SVBR-100 reactor is planned to be constructed near the SSC RIAR (Dimitrovgrad) The first criticality is scheduled to be reached in 2017 IAEA HQ, Vienna, Austria, May 19-23,

43 IAEA HQ, Vienna, Austria, May 19-23, SVBR-100 BASIC PARAMETERS Parameter Value Thermal power, MW 280 Electric power, MW Fuel/enrichment, % UO 2 /16 Primary circuit coolant Lead-Bismuth Fuel campaign duration, year 7-8 Reactor module dimensions (diameter/height), m 4.53/7.55

44