俄罗斯高温气冷堆.doc

俄罗斯高温气冷堆.txt遇事潇洒一点，看世糊涂一点。相亲是经销，恋爱叫直销，抛绣球招亲则为围标。没有准备请不要开始，没有能力请不要承诺。爱情这东西，没得到可能是缺憾，不表白就会有遗憾，可是如果自不量力，就只能抱憾了。 本文由mtlzc2010贡献 pdf文档可能在WAP端浏览体验不佳。建议您优先选择TXT，或下载源文件到本机查看。 1 Development of HTGR technologies in Russia: experience, activities, plans Prepared by OKBM, Nizhniy Novgorod and RRC Kurchatov Institute, Moscow Presented by A. Sedov, RRC Kurchatov Institute, Moscow = Villigen, PSI November 27, 2009 HTGR APPLICATIONS Weapons Plutonium TRISO Electricity Co-generation : Ammonia production Ethylene production Petroleum processing Synthetic fuel production Hydrogen LWR Spent Fuel TRISO TRISO Fuel in graphite blocks Pu, U-Pu, U-Th, LEU TRISO Reactor GT-MHR 3 HTGR PROJECTS: EXPERIENCE AND ONGOING Design of a test-industrial 2-circuit nuclear installation with the steam-turbine cycle for development of HTGR technologies (1971 1984) Final Design of a pilot-industrial nuclear power plant for generation of process heat and electricity in the steam-turbine cycle (19731987) Final Design of a pilot-industrial nuclear power plant of modular concept for generation of process heat and electricity (1987 1992) GT-MHR VGM VG-400 VGR-50 Design of a gas-turbine modular helium reactor for generation of electricity in the direct closed gas turbine cycle with burn up Pu fuel (development started in 1995) MHR-T Conceptual design of a nuclear power plant for generation of process heat for hydrogen production and electricity in the direct gas-turbine cycle (2004) 4 RUSSIAN TEAM OF DEVELOPERS Rosatom OKBM - Customer - GT-MHR chief designer of reactor plant and organization responsible for entire project development - GT-MHR general designer of NPP - Project scientific supervisor - Chief designer technologist of fuel compact development - Mastering and transfer of compacting and coating application technology - Fuel irradiation tests and post-irradiation examinations VNIPIET RRC “Kurchatov Institute” VNIINM NPO Lutch NIIAR 5 VGM REACTOR PLANT 1 reactor core; 2 vessels block; 3 intermediate heat exchanger; 4 steam generator; 5 gas circulator; 6 emergency cooldown system; 7 fuel reloading system; 8 RSS; 9 helium purification system; 10 relief valve N=200 MW (th); Tinlet=300C; Toutlet=950C; P=5P; Core-pebble bed 6 Helium Loop PG-100 in Reactor MR (Kurchatov Ins) Reactor Power, MW Pressure of Helium Coolant, MPa Flow Rate, g/s - in the Loop - in Test Channel Helium leakage, %/day oC Temperature of Helium, - in the Loop - in Test Channel - in Test Section Temperature of fuel in CPs oC Duration of irradiation period h Fluence of fast neutrons, n/cm2 Burnup (FIMA) % 27 - 33 3.8 4.1 230 - 250 38 - 100 0.25 0.5 15 150 150 600 300 600 500 - 900 13 500 0.7 12*1021 4.9 12 1 Reactor pool; 2 Core; 3 Test Channel; 4 Receiver, 5 Safety membrane; 6 Pressure reductor; 7 Shutdown gas receiver; 8 Recuperator; 9 11 Helium Blowers; 12, 13 Heat Exchangers; 14 Heater; 15 Copper oxidizer; 16 Cooler; 17 Decaying GFP storage; 18 Zeolite Filter; 19 Regenerator; 20 Cryogen Graphite Filter; 22, 23 HXs; 24 Metalceramic Filter; 25 Vacuum Pump; 26 Safety membrane; 27 Receiver; 28 Control Valve; 29 Safety valve; 30 - Vacuum Pump; 31 Accident Receiver 7 In Pile Test Channels in Helium Loop PG-100 8 POSSIBLE OUTLINE OF HIGH-TEMPERATURE REACTOR TECHNOLOGY DEVELOPMENT IN RUSSIA Commercial nuclear cogeneration plant Main nuclear cogeneration plant Commercial NPP Main NPP FGR GT-MHR Demonstration gasgasturbine modular helium reactor for highly efficient generation of electric power Demonstration module for power technology application and production of hydrogen MHR-T Demonstration highhightemperature fast gasgascooled reactor for electric power and/or hydrogen production Fuel production Reactor and power conversion system technologies Fuel technology High-temperature heat exchanger technology Hydrogen production technology Modular helium reactor is the basis for implementation of various HTGR technologies 9 MAIN AREAS OF GT-MHR PROJECT ACTIVITIES High-burnup fuel Fission products transport with experimental validation and upgrading of computer codes and data bases Experimental and analytical validation of reactor neutronic characteristics, verification of computer codes Reactor system Power conversion system Designs of components and systems 10 GT-MHR REACTOR SYSTEM Reactor key features CPS assembly Reactor vessel Reactor core Integral layout of the reactor equipment inside a single vessel Annular reactor core Reactor fuel in the form of multi-layer coated particles compacted in graphite fuel elements Passive removal of residual heat Possible reactor transition for one fuel cycle to another using various fuel types (U, Pu, Th, MOX) Stack IVM Hot gas duct Main technical characteristics Thermal capacity, MW(th) Helium temperature at the reactor inlet, C Helium temperature at the reactor outlet, C Reactor inlet pressure, MPa Helium flowrate, kg/s Fuel assembly Prismatic Fuel block 600 490 850 7.126 318.9 Lower plenum SCS unit 11 GT-MHR POWER CONVERSION SYSTEM PCU key features Generator Diaphragm coupling Gas cooler Integral layout of PCU equipment inside a single vessel Vertical TM layout Diaphragm coupling between electrical generator and TC rotors TM rotor electromagnetic suspension Generator helium cooling Recuperator efficiency 0.95 Direct Bryton Cycle with recuperator and intercooler Turbocompressor IVM Basic technical characteristics Recuperator Precooler Intercooler Generator power, MW Helium temperature at the PCU inlet, 0C Helium temperature at the PCU outlet, 0C Helium pressure at the PCU inlet, MPa Helium pressure at the PCU outlet, MPa 287 850 490 7.03 7.12 12 MHR-T ENGINEERING CONCEPT (HTE OPTION) The MHR-T reactor plant was developed based on the GT-MHR reactor design Main technical characteristics (HTE option) Thermal power, MW Power for hydrogen production - electric, MW - thermal, MW 600 Temperature at the reactor outlet, 0 950 205.5 160 54.05 60 Hydrogen output, Life time, years thousand tons / year Power conversion unit Reactor High-temperature heat exchangers HTRG TEST FACILITIES in RUSSIA Facilities for fuel experimental investigations testing TRISO fuel fabrication technology quality control and investigate the fabricated fuel irradiation and post-irradiation examinations Facilities for experimental investigations of reactor system and reactor core Facilities for experimental investigations in support of RS component testing Facilities for power conversion system experimental investigations investigations of rotor dynamics and electromagnetic suspension test TC and generator components Facilities for experimental investigations of fission product transport Hydrogen production technology investigations A Few Examples of Existing HTGR Experimental Facilities Within the framework of HTGR program, about 80 test facilities have been established in OKBM, RRC KI, VNIINM, NIIAR, NPO “Lutch” etc. to investigate technological processes and to test main reactor plant components. Small helium loop, power 500 kW, temperature to 9500C (OKBM) Bench-Scale Facility (VNIINM) BFS physical test facility (IPPE) ASTRA critical test facility (RRC KI) Complex of test rigs for tests of electromagnetic suspension system (OKBM) The lab-scale facility for fabrication of Ufuel (NPO “Lutch”) Test facility for mockup tests of CPS drives (OKBM) Gas-dynamic test facility (OKBM) 15 EXISTING HTGR EXPERIMENTAL FACILITIES Test facility 1 2 3 4 5 6 7 8 9 10 11 12 13 BENCH-SCALE FACILITY (VNIINM) COATING EQUIPMENT (NPO LUTCH) Purpose Fabrication and certification of GT-MHR fuel Manufacturing fuel particle coatings and fuel compacts with non-irradiated uranium Description glove boxes Dense pyrocarbon, Silicon carbide, Porous pyrocarbon, Fuel kernel Fuel particle type TRISO, Tmax=12001600 Aerosol, volatile, solid radionuclides; , radiation Enrichment in U235-90%, neutron flux 8*1017 n/cms Core volume 47.4 L, U235 in a batch with fresh FAs 4.35kg SM-3: =up to 1,8 *1015 cm-2s-1 RBT-6: =up to 5,6 *1013cm-2s-1 Glove boxes with various equipment for post-Irradiation tests Various options for core geometry Graphite stack up to 4.5 m, graphite blocks 250250 mm Reactor core (D/H)-2.2/2.2m, FA type-hexagonal Telescopic bar, CPS drive position sensor Maximum helium pressure 5MPa, and temperature 950 Electric capacity 15MW, temperature up to 965C PARAMETR TEST FACILITY COMPLEX Investigate thermomechanical and corrosion behavior of fuel elements (NPO LUTCH) OSA TEST FACILITY (RRC KI) GIDRA REACTOR (RRC KI) IR-8 POOL-TYPE REACTOR (RRC KI) SM-3 AND RBT-6 RESEARCH REACTORS(NIIAR) POST-IRRADIATION TEST COMPLEX (NIIAR) ASTRA CRITICAL NUCLEAR TEST FACILITY (RRC KI) GROG CRITICAL NUCLEAR TEST FACILITY (RRC KI) BIG FAST CRITICAL FASILITY (IPPE) CONTROL ROD DRIVE MOCKUP TEST (OKBM) HELIUM TEST FACILITY ST-1565 (OKBM) LARGE-SCALE HIGH-TEMPERATURE HELIUM TEST FACILITY ST-1312 (OKBM) Measure fission product release Test fuel elements from various reactor plants in reactivity accident conditions Nuclear physics, radiochemistry radiobiology, and activation analysis Irradiation examinations of fuel elements, reactor material researches Investigate the irradiated articles, properties of irradiated fuel, structural, moderating and absorbing materials Experiments in the cold and hot conditions Investigate the GT-MHR neutronic characteristic Validate the GT-MHR neutronic characteristic Investigate telescopic technology, check movable components operability Tests of steam generator and heat exchanger models, valves, thermal insulation, relief valves, mixer models, HPS, gas circulator Test of models of steam generator and high temperature heat exchangers, gas circulator 14 16 EXISTING HTGR EXPERIMENTAL FACILITIES Test facility 15 16 17 Purpose Description 18 19 20 21 22 23 24 MAIN CIRCULATOR TEST FACILITY ST- Tests of a full-scale primary gas circulator, valves Pressure 4.9MPa, flowrate 95kg/s 1383 (OKBM) and the other equipment of HTGRs Air Tests of the Full-Scale Recuperator Heat AIR TEST FACILITY (OKBM) Flow rate 10000 m/h Exchanger Element Verify rotor dynamics, check critical frequency, ROTOR SCALED MODEL (OKBM) rotor model behavior, balancing in electromagnetic Rotor length 10.5 m, weight 1000 kg suspension MINIMOCKUP OF ROTOR ON FULL Investigate rotor dynamics, develop control laws 1 axial and 2 radial EMB, rotor rotation ELECTROMAGNETIC SUSPENSION and algorithms, verify computer codes speeds 0-10000 rpm, 4 critical frequencies (OKBM) TEST FACILITY FOR EMB Measure characteristics of radial EMB, Investigate Rotor length 1.4m, weight 250kg, load to CHARACTERISTIC INVESTIGATIONS influence of control system EMB up to 800kg (OKBM) Excitation frequency range TEST FACILITY FOR SENSOR Investigate sensor operation modes at variation of INVESTIGATIONS (OKBM) excitation frequency and specific gap value 1 - 400 kHz AXIAL CATCHER BEARING SEGMENT Investigations of gas-static characteristics of one Helium pressure upstream the segment 1.1 (OKBM) axial TM CB segment 6.0 MPa Pressure up to 4.9 MPa, axial/radial load L-1129. FRICTION COUPLES TESTS Select materials and wear-resistant coatings 1.2/1.4 MPa (OKBM) STATOR SEAL TEST (OKBM) Determine values of air leaks across the seal Pressure drop 0.010.4MPa SORPTION AND DIFFUSION ON Investigate silver/cesium diffusion and sorption on Working temperature range 400-900 STRUCTURAL MATERIAL SAMPLES structural materials (NPO Lutch) TsGS CIRCULATION HELIUM TEST Gas pressure 1.5 -10atm, temperature 50Investigate helium technology and HTGR materials 25 FACILITY (RRC KI) 900 KhTS CHEMO-THERMAL FACILITY (RRC KI) TEST Investigate technology of hydrogen production from water and methane using HTGR heat Gas pressure 10MPa, temperature in the conversion sector 900 26 17 FUEL FABRICATION TECHNOLOGY DEVELOPMENT BENCH-SCALE FACILITY (VNIINM) Bench-Scale Facility; kernel production sector Purpose Technology development, fabrication and certification of an experimental GT-MHR fuel batch in order to validate the fuel compact design and operability. Completed The facility consists of several glove boxes including all equipment necessary to fabricate kernels, coated fuel particles, and fuel compacts, and to control their quality. Status The first stage of BSF construction was completed; first batches of natural uranium kernels, coated fuel particles and fuel compacts were fabricated. 18 GT-MHR FUEL Operation Parameter 1 Fuel type 2 Power of Fuel Compact, KW: - average - maximum 3 Average fuel lifetime, EFPD 4 Maximum fluence of fast neutrons ( 0,18 EV) for an operating period, n/m-2 5 Fuel burnup, MWday/kg Pu: Average - Maximum 6 Maximum fuel temperature, : - normal operation conditions - design-basis accident conditions, 100 hr 7 Admissible fraction of with damaged SiC a layer Value TRISO,kernels with outer oxygen getter (SiC) 0,206 0.600 (280 d.) 870 (3290) 51025 750 930 1250-1300 1600 Less than 110-4 COMPLEX OF FUEL IRRADIATION TEST REACTORS IN NIIAR RBT-6 Research Reactor 19 SM-3 Research Reactor Capabilities to Study HTGR Physics at the ASTRA Critical Facility of RRC “Kurchatov Institute” Out-of-Pile Loop - TsGS Helium Circulation Test Facility (RRC KI) Purpose Investigate helium technology and HTGR materials. Upgrade the test facility for out-of-pile loop tests of fission product transport Main technical characteristics Electric power, kW Gas pressure, atm. Gas temperature, Circuit volume, m3 Gas circulator head coefficient Motor rotation speed, rpm Helium heating in the compressor, Maximum helium flow rate at 10 atm., kg/s Volumetric helium flow rate at 50 0C and 10 t., m3/s 75 1.5 10 50 900 0.9 1.03 2950 up to 80 0.01 0.065 Status Under inspection before planning Upgrade 22 FISSION PRODUCT TRANSPORT: WORKS and PLANS Fission Product Transport Modification and elaboration of FPT codes FPT Lab-scale tests Lab-scale tests of fission products diffusion and decontamination Investigations of SiC (ZrC) oxidation parameters and fission products solubility FPT out-pile loop tests Development of the project of facility for SFP out-of-pile reactor loop tests FPT irradiation tests FPT irradiation tests at RBT-6 and SM-3 reactors FPT postirradiation tests with annealing FPT postirradiation tests with annealing in NIIAR FPT in-pile loop tests FPT computer code validation and sertification FPT computer code validation and sertification FPT codes modification and upgrade based on test results Elaboration of new mechanistic models and coupling their in Program Complex Test facility manufacture for FPT out-pile loop tests Design of test facility for FPT in-pile loop tests Lab-scale tests of fission products transport and plate-out FPT out-pile loop tests Test facility manufacture for FPT in-pile loop tests FPT in-pile loop tests Note: Red font work is underway Blue font planned activities INTEGRATED SET OF COMPUTER CODES (RELIABLE MODELING) Initial data for all codes ENDF-B, JEF, JENDL, UKNDL, FOND 2.2, WLUP nuclear data Multigroup micro cross-section library VITAMIN-B6, VITAMIN-C 23 NJOY ASTRA AMPX Group macro crosssection Fuel thermo-dynamic characteristics WIMS, UNK MCNP ORIGEN MONTEBURNS, MCU GOLT Fuel thermomechanical characteristic