核反应堆热工水力研究室Xi'anJiaotongUniversityXJTU-NuTHelNuclearThermal-hydraulicLaboratoryThermal Hydraulic R&D of ChineseAdvanced Reactors810-NUTHEL张大林2021.041759
1/59 Xi’an Jiaotong University Thermal Hydraulic R&D of Chinese Advanced Reactors 810-NUTHEL 张大林 2021.04
核反应堆热工水力研究室Xi'an Jiaotong UniversityXJTU-NuTHeLNuclearThermal-hydraulicLaboratoryOutlineBackground for thedevelopment of Chinese advancedreactorsBriefIntroduction to Chinese advanced reactorsA2.1 CAP14002.2 Hualong-12.3 ACP100N2.4 SCWRN2.5 CLEAR-I>2.6 TMSRV2.7HTR-PM?Conclusions2/59
2/59 Xi’an Jiaotong University Outline 1 Background for the development of Chinese advanced reactors 2 Brief Introduction to Chinese advanced reactors 3 Conclusions ➢ 2.1 CAP1400 ➢ 2.2 Hualong-1 ➢ 2.3 ACP100 ➢ 2.4 SCWR ➢ 2.5 CLEAR-I ➢ 2.6 TMSR ➢ 2.7 HTR-PM
核反应堆热工水力研究室Xi'anJiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulicLaboratoryl.Background forthedevelopment of Chinese advancedreactorsN OverviewoftheGenerationsofNuclearEnergySystemsnationaGenerationIForumGenerationGenerationIIEartyPrototype++CommercialPowerReactorsGenerafionI+ReactorsAdvancedGenerationIVLWRSEvolutionaryDesignsOffering-HighlyImprovedEconomicalEconomicsfor-EnhancedNear-TermSafety-ShippingportDeploynent-Minimal-Dresden,FermiWasteABWR-Magnox-Proliferation-LWR-PWR.BWR-System80+Resistant-CANDU-AGRGenIllGenIlI+GenN195019601970198019902000201020302020Economic&SafetyStandardizationSustainability&Serialization3/59
3/59 Xi’an Jiaotong University 1. Background for the development of Chinese advanced reactors ➢ Overview of the Generations of Nuclear Energy Systems Standardization & Serialization Safety Economic & Sustainability
核反应堆热工水力研究室Xi'anJiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulicLaborator1.Background for the development of Chinese advanced reactors>ThreestagesofdevelopmentofChinesenuclearpowerStage 1Stage 2Stage 3200420111978AcceleratedHighlyefficientFirstNPPdevelopmentdevelopmentMedium-and long-termdevelopment plan ofFukushima accidentChina nuclear powerQinshanNPPNuclear safety(2005-2020)Severe accidentprevention andDaya BayNPPmitigationPassivesafetytechnology.14/59
4/59 Xi’an Jiaotong University 1. Background for the development of Chinese advanced reactors ➢ Three stages of development of Chinese nuclear power Stage 1 Stage 2 Stage 3 First NPP Accelerated development Highly efficient development Qinshan NPP Daya Bay NPP Medium- and long-term development plan of China nuclear power (2005-2020) Fukushima accident Nuclear safety Severe accident prevention and mitigation Passive safety technology
核反应堆热工水力研究室Xi'an JiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulicLaboratoryl.Background forthedevelopment of Chinese advanced reactorsNGoalsforChineseadvancedreactorsandSelectionsThe Chinese government sponsors a program of research, development, anddemonstration related to advanced reactors. both small modular reactors andlargersystemsTheseadvanced reactorsencompass innovative reactorconceptsCAP1400 - Chinese large AdvancedPassivepressurizedwaterreactorHualong-1 -Chinese large advancedactive andpassive pressurized waterSafety and ReliabilityreactorAcP1oo-ChinesesmallmodularreactorGoalsEconomicsScwR-Super critical water-cooled reactorinChinaSustainabilityCLEAR-Chineselead-cooledfastreactorTMsR-ChineseThoriummolten-saltreactorHTR-PMHigh-temperature-reactorpebble-bed modules575
5/59 Xi’an Jiaotong University 1. Background for the development of Chinese advanced reactors ➢ Goals for Chinese advanced reactors and Selections Sustainability Economics Safety and Reliability Goals ◆ The Chinese government sponsors a program of research, development, and demonstration related to advanced reactors, both small modular reactors and larger systems ◆ These advanced reactors encompass innovative reactor concepts ⚫ CAP1400 - Chinese large Advanced Passive pressurized water reactor ⚫ Hualong-1 - Chinese large advanced active and passive pressurized water reactor ⚫ ACP100 - Chinese small modular reactor ⚫ SCWR- Super critical water-cooled reactor in China ⚫ CLEAR - Chinese lead-cooled fast reactor ⚫ TMSR - Chinese Thorium molten-salt reactor ⚫ HTR-PM - High-temperature-reactor pebble-bed modules
核反应堆热工水力研究室Xi'anJiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulicLaboratoryOutlineBackground forthedevelopment ofChinese advancedreactorsBriefIntroduction to Chinese advanced reactors2.1 CAP14002.2 Hualong -12.3 ACP1002.4 SCWR2.5 CLEAR-I2.6 TMSR2.7 HTR-PMConclusions6/5
6/59 Xi’an Jiaotong University Outline 1 Background for the development of Chinese advanced reactors 2 Brief Introduction to Chinese advanced reactors 3 Conclusions ➢ 2.1 CAP1400 ➢ 2.2 Hualong -1 ➢ 2.3 ACP100 ➢ 2.4 SCWR ➢ 2.5 CLEAR-I ➢ 2.6 TMSR ➢ 2.7 HTR-PM
核反应堆热工水力研究室Xi'an Jiaotong UniversityXJTU-NuTHeLNuclearThermal-hydraulic Laboratory2. Brief Introduction to Chinese advanced reactors2.1 CAP1400CAP14oo is China AdvancedPassive nuclear powerplant with installed capacityreachingto1400MW(CAP1400)whichisindependentlydesignedastheChina'sstate-of-the-art third generation nuclear power brand based on AP1000 technologydigestion and absorptionCAP1400 adopts balanced design of plant system, enhanced configuration &capacity of safety systems and key equipment, further improved safety designmarginPCCS gravity drain water tanNatural convection air dischargeWater film evaporatiorOutside cooling air intakeInternalcondensationndSteelcontainment vesselBatural recirculationAirbafleFrom SNPTC
7/59 Xi’an Jiaotong University 2. Brief Introduction to Chinese advanced reactors 2.1 CAP1400 ◆ CAP1400 is China Advanced Passive nuclear power plant with installed capacity reaching to 1400 MW (CAP1400) which is independently designed as the China’s state-of-the-art third generation nuclear power brand based on AP1000 technology digestion and absorption ◆ CAP1400 adopts balanced design of plant system, enhanced configuration & capacity of safety systems and key equipment, further improved safety design margin From SNPTC
核反应堆热工水力研究室Xi'an JiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulicLaboratory2.Brief Introduction to Chinese advanced reactors2.1 CAP1400Several Key Tests for design verification, safety review and software developmentwereperformedThe ACME (Advanced Core-coolingMechanism Experimenthasthesame2-loopreactorcoolant system and passive safetysystem configuration as theCAP1400, and the purpose ofACME is to simulate the integralsystem response after the end ofthe first blowdown phase duringSBLOCAACMEComprehensiveTestLoopPXs8/59From SNPTC
8/59 Xi’an Jiaotong University 2. Brief Introduction to Chinese advanced reactors 2.1 CAP1400 ➢ Several Key Tests for design verification, safety review and software development were performed ACME Comprehensive Test Loop PXS ◆ The ACME (Advanced Corecooling Mechanism Experiment ) has the same 2-loop reactor coolant system and passive safety system configuration as the CAP1400, and the purpose of ACME is to simulate the integral system response after the end of the first blowdown phase during SBLOCA From SNPTC
核反应堆热工水力研究室Xi'an JiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulic Laboratory2.BriefIntroduction to Chinese advanced reactors2.1 CAP1400CERTTestLoopPCSHydraulic Simulation Test LoopSGSteam-waterSeparationFull-scaleIn-Vessel9/59FromSNHot PerformanceTest LoopRetention TestLoop
9/59 Xi’an Jiaotong University 2. Brief Introduction to Chinese advanced reactors 2.1 CAP1400 CERT Test Loop PCS Hydraulic Simulation Test Loop SG Steam-water Separation From SNPTC Hot Performance Test Loop Full-scale In-Vessel Retention Test Loop
核反应堆热工水力研究室Xi'an JiaotongUniversityXJTU-NuTHeLNuclearThermal-hydraulic Laboratory2.Brief Introduction to Chinese advanced reactors2.1 CAP1400ADS-4 entrainment and upper plenum entrainment experiments-ADETEL88To atmosphere?OADS-4entrainmentOOL4Weighing tankO Discharge line0Nitrogen nozzleTeebranchtestsectiorVenting linePressurevesselDeionized water?Bvpasslinecharging systemAir ReceiverBypass lineaF-2FilterF-CCOHCFeed pumpOControl valvePreheater Flow meterOPumpDd?FilteF-3Drain outlefWater tankAir CompressorTest schematic diagramUpper plenum entrainment10/59
10/59 Xi’an Jiaotong University 2. Brief Introduction to Chinese advanced reactors 2.1 CAP1400 ➢ ADS-4 entrainment and upper plenum entrainment experiments-ADETEL ADS-4 entrainment Upper plenum entrainment Test schematic diagram DP-1 P-1 T-5 L-1 L-2 DP-3 DP-4 T-3 T-4 T-7 Air Compressor Air Receiver Bypass line T-1 T-6 T-2 Filter P-4 Air dryer Control valve Preheater Flow meter Bypass line Tee branch test section To atmosphere Discharge line Nitrogen nozzle Pump Filter Drain outlet Pressure vessel Weighing tank Venting line Feed pump DP-2 Water tank P-3 P-2 F-1 F-2 F-3 F-4 Deionized water charging system L-3