SMART. OECD/NEA-IAEA Joint Expert Workshop. For Electricity Generation and Desalination. April 4, 2013 Paris, France

Transcription

1 1 OECD/NEA-IAEA Joint Expert Workshop SMART For Electricity Generation and Desalination April 4, 2013 Paris, France SMART PM Keung Koo Kim Advanced Reactor Development

2 Outline I. SMART for Dual Application II. SMART Development III. SMART Characteristics IV. Summary 2

3 I. SMART for Dual Application SMART System integrated Modular Advanced ReacTor 3

4 SMART Application 330MW th Integral PWR Electricity Generation, Desalination and/or District Heating Intake Facilities SMART Steam Transformer Steam Electricity Plant Data Power : 330 MWt Water : 40,000 t/day Electricity: 90 MWe Seawater Potable water Desalination Plant System-integrated Modular Advanced ReacTor Electricity and Fresh Water Supply for a City of 100,000 Population (Korean) Suitable for Small Grid Size or Localized Power System 4

5 Safety Requirements for Desalination Any form of radioactive particles shall not be transferred to the distillate Suitable means shall be considered to do Radioactivity in main steam line shall be monitored on real time When radioactive material is detected in main steam line, desalination plant shall be shut-down for inspection. Turbine Generator Backpressure Extract Steam Steam Transformer (Physical Barrier to prevent Radioactive material Transfer) 5

6 SMART Desalination System MED Desalination 40,000 ton/day + 90 MWe (Optimal) 4 Units of MED-TVC (10 Effects) Steam Extract from Turbine 77,000 ton/day + 3 MWe Back Pressure Turbine MED Desalination Plant Schematic Diagram of MED-TVC 6

7 Desalination Design 7

8 Electric Power Generation (MWe) District Heating Heat Generation (Gcal/hr) District Heating 147 Gcal/h of Heat Supply to Local Area Heating + 2 MWe Supply of Electricity and 5 C Hot Water for 100,000 Populations - Based on Korean Peak Electric Power and Heat Usages Expected design point for 5 o C hot water LP TBN Exit Pressure (bar)

9 II. SMART Development SMART System integrated Modular Advanced ReacTor 9

10 Development History Conceptual Design Basic Design SMART-P (65MWt) Development Pre Project Design Optimi zation SMART Standard Design Approval Domestic Const. & Export Total 1500MY and ~300M$ are invested 10

11 Design & Licensing Validation Tests Methodology Hardware SMART Development Normalized Axial Velocity Blockage Center Line (1.75 in) Measured COBRA (Uniform Axial Noding) MATRA (Nonuniform Axial Noding) Axial Location from Rod Bundle Inlet (in) Predicted Critical Mass Flux [kg/m 2 s] 100k 10k 1k 1k 10k 100k Reactor Design Methodology Topical Report for Licensing Approval System Design and Analysis Methodology, Fuel Design Technology Henry and Fauske Model U blocked /U bundle +40% KAERI (w/o NC) KAERI (with NC) Celata et al. (w/o NC) -40% Celata et al. (with NC) Measured Critical Mass Flux [kg/m 2 s] Computer Program Development Improvement/ Applicability Evaluation Verification SSAR, CDM, ITAAC, etc SMART-330 NSSS Basic Design More than 4,000 design & Licensing Documents SMART Basic Design Standard Design License SDA Constructio n Separate Effect Tests MMIS Essential Tech. Verification Tests Small Scale Hi Temp. & Pres. Tests Separate Effect Tests for Transients Digital Safety System Verification Tests Integral T/H Verification Tests Mockup Tests S/G, RCP, CRDM, etc. S/G, RCP, CRDM, etc. Small Scale Component Tests Fuel Development & Test 11 11

12 DNBR 10 O MS FW A B C N N D E 90 O O F G w/o U FA 4.0 w/o U FA N indicates No. of Gd rod 피동잔열제거계통 ECT PRHRS HX Limit DNBR = 1.41 H Containment J SLB Feed Flow Increase STEAM Flow Increase FLB CEA Withdrawal CLOF Locker Rotor SGTR Time, sec 0 O RDT RV LHX RHX IRWST Water Level, m 화학및체적제어계통 Pressure, MPa LETDOWN CONTROL VALVE M EDT F CHARGING CONTROL VLAVE BRM PRM M RDP M PIX Chemical Addition System CCP M PHIX VCT M M 정지냉각계통 SIP GS 안전주입계통 OUTSIDE (YARD) BAST HUT BABT HUP BAC RMWP EDUCTOR BAMP SCP SCHX BA CIX RMWT Time, sec FLB CLOF CEA Withdrawal Locked Rotor SLB SGTR RV Collapsed Water level Top of Core Hot Spot Cad Surface Temperature Pressure Limit = 1.7 MPa Time, sec Temperature, K Standard Design 증기 발생 기 급수구역격리밸브 증기구역격리밸브 증기구역격리밸브 급수구역격리밸브 급수격리밸브 급수격리밸브 주증기격리밸브 주증기격리밸브 급수펌프 기동우회냉각기 급수펌프 우회증기냉각기 우회증기냉각기 비상보충수탱크 비상보충수탱크 기동우회냉각기 C P P C P P 복수펌프 복수기 복수기 터빈발전기 터빈발전기 냉각탑 순환수조 2 차측기기 순환수펌프 복수펌프 2 차측냉각수펌프 NSSS Design Fuel Design Component Design BOP/AE Design Core Design Main Feedwater and Main Steam Fuel Design Mechanical Design Component Design System Design General Arrangement Component Design Analysis MMIS Design Containment Building Over 1500 Simulations Confirm Safety SBLOCA DNBR Pressure Safety Analysis Fuel Assembly Design Equipment Vendor Survey Aux. system Design 12

13 Technology Validation Design Data Safety Tests Technology Validation Tools & Methods Performance Tests Standard Design Core SET Freon CHF Water CHF Safety SET Safety Injection Helical SG Heat Transfer Condensation HX Heat Transfer Integral Effect Tests VISTA SBLOCA SMART-ITL Digital MMIS Control Unit Platform Communication Switch Integral Safety System Code Devel/V&V Safety: TASS/SMR-S Core TH: MATRA-S Core Protec./Monitor. Design Methodology DNBR Analysis Accident Analysis (SBLOCA, LOFA, ) Integral Rx Dynamics V&V Technical Reports Fuel Assembly Out-of-Pile Mech./Hydr. RPV TH RPV Flow Distribution Flow Mixing Header Ass. Integral Steam PZR PZR Level Measurement Components RCP Hydrodynamics RPV Internals Dynamics SG Tube Irradiation Helical SG ISI In-core Instrumentation Digital MMIS MMI Human Interface Control Room FSDM Standard SAR Standard Design Approval 13

14 Core & Fuel TEST Fuel Spacer Grid Measurement s TEST Section TEST Section Fuel Performance Tests CHF Measurement Test 14

15 Fuel Mechanical Performance Test Impact TEST Vibration TEST Bending TEST 15

16 Mechanics and Components Dynamic Test RCP TEST Loop TEST Facility Low Friction Cable RPV Dynamics Tests, RCP Mockup Test and Helical ISI Test SG Tube Material (A690) Irradiation Test 16

17 Thermal-Hydraulics Experiment PRHRS Heat Ex. Pressurizer Safety Injection VISTA Thermal-Hydraulic Performance Tests 17

18 SMART ITL(Integral Test Loop) World s Unique and Largest Full Scope Accident Simulation - 1:1 Height, 1/49 Volume 1

19 Man-Machine Interface System Digital Main Control Room Validation - FSDM (Full-scope Dynamic Mockup) * It s Real Photo, not Graphics Real Operators in FSDM 19

20 Licensing Pre-application Review by KINS (Feb. 2010) Application of Standard Design Approval (Dec. 30, 2010) CDM, SSAR, EOG and related documents Document Conformance Evaluation (~Feb. 2011) 1 st Round Questionnaire : April 30, nd Round Questionnaire : July 31, rd Round Questionnaire : October, th Round Questionnaire : December, 2011 Additional Questionnaire: January ~ April, 2012 Standard Design Approval : July 4,

21 III. SMART Characteristics SMART System integrated Modular Advanced ReacTor 21

22 Integral Reactor Loop Type PWR Pressurizer Canned Motor Pump X X X X X X Core Helical Steam Generator Enhanced Reactor Safety: No LBLOCA 22

23 Reactor Vessel Assembly Steam Generator ICI Nozzles Control Rod Drive Mechanism Pressurizer Reactor Coolant Pump Upper Guide Structure Core Support Barrel Flow Mixing Header Ass y Core Steam Nozzle Feedwater Nozzle No large RPV penetrations Less than 2 inch penetrations In-Vessel Steam Pressurizer Helical Steam Generators Once through SG Produce superheated steam 4 Reactor Coolant Pumps Canned motor type Horizontally mounting 57 Fuel Assemblies Standard 17x17 UO 2 (< 5 w/o U 235 ) w/ reduced height (2m) Performance proved at operating PWRs 23

24 RPV - Internals 24

25 Balance of Plant Containment Building Hydrogen Recombiner: 12 Passive Autocatalytic Recombiners Containment Spray System (2 Train) Containment Isolation System Aircraft Impact Proof EDG Bldg Auxiliary Building Quadrant Wrap-around Fuel Building Inside Aircraft Impact Proof TBN Bldg Single Basemat with Containment (Seismically Resistant) Aux. Bldg Containmen Composite Bldg 25

26 General Arrangement Single Unit Construction 300 x 300m for Power System Twin Units Construction ~20% More Economical than Single Unit 26

27 Enhanced Safety Passive Residual Heat Removal system - 20 days grace period against Fukushima-type accident Passive Hydrogen Removal System - Prevent Hydrogen Explosion Containment Building - Air craft (Boeing767) Crash Proof - Low Hydrogen Concentration Minimize Fuel Failure - Fuel submerged during all DBA Passive Ex-Vessel Cooling - Prevent Vessel Failure 27

28 SMART vs. Fukushima Station Blackout Event Grace Time Scenario PRHRS 1 Yes Grace Time * 20 Days** 2 No 2.6 Days Rx Shutdown Recharge ECT EDG STOP Blackout Core Cooling EDG Start Batteries Rx Overheat ( hours) Fukushima 2

29 IV. Summary SMART System integrated Modular Advanced ReacTor 29

30 Summary Multiple Application Electricity generation, seawater desalination, district heating and process heat to industries Safe in Fukushima Accident Condition The core is maintained undamaged for up to 20 days without any corrective actions by the operator First to the Market The standard design of SMART and Technology Validation was completed Standard design approval was granted on July 4,

31 Thank You!! SMART System integrated Modular Advanced ReacTor 31