SMART. Design and Technology Features for both Electric & Non-Electric Applications

Transcription

1 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment, 4~8 July 2011, Vienna, Austria Design and Technology Features for both Electric & Non-Electric Applications Keun Bae Park Technology Development

2 Contents Features of Current Status of Project The Safety of Perspectives and Closing Remarks System-integrated Modular Advanced ReacTor 2

3 Contents Features of Current Status of Project The Safety of Perspectives and Closing Remarks : System-integrated Modular Advanced ReacTor System-integrated Modular Advanced ReacTor 3

4 SMR Solutions to Global Energy Issues Small & Medium Reactors (SMR) offer Several Advantages Enable enhanced safety features (robustness) - Easier implementation of advanced safety features - Small source term and passive safety Suitable for small or isolated electrical grids Lower capital cost per unit - Small financial risks - Makes nuclear energy feasible for more utilities and energy suppliers Siting and co-generation flexibilities Just-in-time capacity addition, Short construction time - Enable to meet electric demand growth incrementally Many realizable SMR concepts proposed are based on the LWR technology and reflection of the past experiences By eliminating the cause of accidents (initiators), instead of controlling accidents (ex. DBAs) Integral PWR fits into these logical requirements System-integrated Modular Advanced ReacTor 4

5 Integral PWR 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 330 MWt (100 MWe) nominal output Small core (57 fuel assemblies) and source term Unit output enough to support electricity, water and heat demand for population of 100,000 Integral PWR with no large RPV penetrations Less than 2 penetrations In-vessel Pressurizer In-vessel Steam Generator Canned Motor Pump Inherent Safety* Elimination of LB-LOCA by design No core uncovery during SB-LOCA Performance proved Fuel Standard 17x17 UO 2 (< 5 w/o U 235 ) w/reduced height (2m) Advanced Grid / IFM design Peak Rod Burnup < 60 GWd/t Performance operating PWRs Improved Core Operability Cycle length: 1,000 EFPD (~ 3 years) Proven reactivity control measures - CRDM, Soluble Boron, BP System-integrated Modular Advanced ReacTor 5

6 Application of 330MW th Integral PWR Electricity Generation, Desalination and/or District Heating Electricity Plant Data Power : 330 MWt Water : 40,000 t/day Electricity : 90 MWe Intake Facilities Steam Transformer Seawater Steam Fresh water Desalination Plant System-integrated Modular Advanced ReacTor 6 System-integrated Modular Advanced ReacTor Electricity and Fresh Water Supply for a City of 100,000 Population Suitable for Small Grid Size or Localized Power System

7 Application of Desalination System 4 Units of MED-TVC to produce 40,000 ton/day + 90 MWe Additional Protection of Possible Radioactive Contamination by Steam Transformer District Heating 147 Gcal/h of Heat Supply to Local Area Heating + 82 MWe Supply of Electricity and 85 C Hot Water for 100,000 Populations - Based on Peak Electric Power and Heat Usages of Korea System-integrated Modular Advanced ReacTor 7

8 NSSS Development Overview Core Design Thermo-hydraulic Design Radiation Protection Nuclear Design MMIS Design Instrument & Control Systems Main Control Room Design Human Factor s Engineering RCS Design Safety Systems Design Water Chemistry Design Thermo-hydraulic Analyses Fluid Systems Design Safety Analysis Performance Analyses Safety Analyses P.S.A. Severe Accident Design Structural Design RCS Arrangement Component Specification Seismic Analyses Mechanical Design Design Integration User Requirements System Integration Pre-operational Test System-integrated Modular Advanced ReacTor 8

9 Nuclear Steam Supply System General Thermal/Electric Power : 330 MWt/100 MWe Design Life Time : 60 Years Design Characteristics Integrated Primary System Passive Residual Heat Removal System Simplified Safety Injection System Long Refueling Cycle : 36 months Full Digital MMIS Technology System-integrated Modular Advanced ReacTor 9

10 RPV and Internals 25 x Mag-Jack CRDM PSV Nozzle CRDM Nozzle 1 x In-vessel Steam Pressurizer Upper Guide Structure ICI Nozzle Core Support Barrel ICI Support Structure Component Cooling Sealing Can Impeller Flywheel Stator Cooler Rotor Diffuser Shaft 8 x Helical Steam Generator Flow Skirt System-integrated Modular Advanced ReacTor 10 1 x Flow Mixing Header Assembly 4 x Canned Motor Pump

11 Control & Protection (Digital MMIS) Fully Digitalized I&C System: DSP Platform 4 Channel Safety/Protection System and Communication 2 Channel Non-Safety System Advanced Human-Interface Control Room Ecological Interface Design Alarm Reduction Elastic Tile Alarm AIS : Alarm and Indication System CEDM : Control Element Drive Mechanism ERF : Emergency Response Facility ICCMS : Inadequate Core Cooling Monitoring System IPS : Information Processing System MCC : Motor Control Center MCP : Main Coolant Pump MCR : Main Control Room NIS : Nuclear Instrumentation System NSGSC : Non -Safety Grade Soft Controller PAM -D : PAM Display PIS : Process Instrumentation System POCS : POwer Control System PPS : Plant Protection System PRCS : PRocess Control System RCR : Rad waste Control Room RSR : Remote Shutdown Room SCOPS : COre Protection System SDCS : SeconDary Control System SGCS : Safety Grade Control System SGSC : Safety Grade Soft Controller SMS : Specific Monitoring System SS : Sub -network Switch TSC : Technical Support Center Safety Shutdown Control Panel RSR RCR TSC ERF PAM-D NSGSC LDP Safety A channel Safety B channel Safety C channel Safety D channel Safety Interface network Non-Safety X channel Non-Safety Y channel Non-Safety Interface network Non-Safety Backbone network Hard-wired connection Logical data flow connection Display such as Information (IPS), Indication (AIS) and Alarm (AIS) Non-Safety Backbone Network SGSC Main Control Panel NSGSC NSGSC SGSC NSGSC Auxiliary Control Panel Safety Interface Network ISO Non-safety Interface Network AIS (PAM B) AIS (PAM A) AIS IPS PPS D PPS C PPS B PPS A PIS D NIS D RTSG D SGCS D PIS C NIS C RTSG C SGCS C SMS B (ICCMS) SMS A (ICCMS) PIS B PIS A NIS B NIS A RTSG B RTSG A SGCS B SGCS A SMS (NIMS) NIS Y NIS X PIS Y PIS X POCS PRCS Y PRCS X SDCS Y SDCS X CEDM Field Sensors Field Sensors Ex-Core Detectors MCC NIMS Sensors Ex-Core Detector Field Sensors MCP MCC MCC System-integrated Modular Advanced ReacTor 11

12 BOP Development Overview Common Mat Design Structural Integrity Design Structural Design of Nuclear Island Radiation Protection Shielding Design Zoning of the Building Bldg. Seismic Analyses Site Characteristic Seismic Analyses BOP Safety System Containment Spray System Hydrogen Control System Containment Bldg. Auxiliary Bldg. TG Bldg. Compound Bldg. General Arrangement System-integrated Modular Advanced ReacTor 12

13 Balance of Plant EDG Bldg TBN Bldg Aux. Bldg Containment Composite Bldg Schematic Diagram of the Secondary System General Arrangement Reactor Bldg & Aux/Compound/EDG Bldg System-integrated Modular Advanced ReacTor 13

14 Balance of Plant Electric System 100% x 2 Emergency DG & Alternate AC Power (Water-tight Bldg) Emergency Battery to Vital Systems for 10 hrs Containment Building Passive Auto-catalytic Hydrogen Recombiners (12) Containment Spray System (2 Trains) Water source from Sump integrated IRWST Containment Isolation System Aircraft Impact Proof Auxiliary Building Quadrant Wrap-around Fuel Storage Inside Aircraft Impact Proof TBN Bldg Single Base-mat with Containment (Seismically Resistant) System-integrated Modular Advanced ReacTor 14 EDG Bldg Aux. Bldg Containment Composite Bldg

15 Balance of Plant Structural Design of Nuclear Island Common mat for Reactor Containment Building and Auxiliary Building Reactor Containment Building Pre-stressed concrete structure Unbonded post tensioning system with 2 buttress Lined with carbon steel plate Provides enough ultimate pressure capacity Maintains structural integrity of cavity in severe accident Auxiliary Building Shear wall concrete structure system System-integrated Modular Advanced ReacTor 15

16 Contents Features of Current Status of Project The Safety of Perspectives and Closing Remarks System-integrated Modular Advanced ReacTor 16

17 Development _ Chronicle Conceptual Design ( ~ 99.03) NSSS Basic Design ( ~ 02.03) -P Development ( ~ 06.02) Pre-Project Service for ( ~ 07.06) Standard Design Approval ( ~ 11.12) NSSS & Desalination Concept (330 MWt) Fundamental T/H Experiment Mock-up Fabrication NSSS Design (330 MWt) Design Methodology & Computer Codes Preliminary Safety Analysis Desalination System 65 MWt Detailed Design Including Fuel, BOP Tech. Verification Tests Safety Analysis 330 MWt, 660 MWt System Optimization Economic Feasibility Study 330 MWt Standard Design Separate/Integral Effect & Performance Tests Design Methodology and Codes Validation To Obtain SDA System-integrated Modular Advanced ReacTor 17

18 Blockage Center Line (18.75 in) MATRA (Nonuniform Axial Noding) k Axial Location from Rod Bundle Inlet (in) 1k 10k 100k 100k 10k Development Path Methodology Reactor Design Methodology Computer Program Development Topical Report for Licensing Approval System Design and Analysis Methodology, Fuel Design Improvement/ Applicability Evaluation Normalized Axial Velocity U blocked /U bundle Measured COBRA (Uniform Axial Noding) Technology Henry and Fauske Model Predicted Critical Mass Flux [kg/m 2 s] +40% -40% KAERI (w/o NC) KAERI (with NC) Celata et al. (w/o NC) Celata et al. (with NC) Measured Critical Mass Flux [kg/m 2 s] Verification Design & Licensing -330 NSSS Basic Design More than 4,000 design & Licensing Documents Basic Design SSAR, CDM, ITAAC, etc Standard Design License SDA Construction Verification Tests 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 Hardware S/G, RCP, CRDM, etc. Small Scale Component Tests Mockup Tests S/G, RCP, CRDM, etc. Fuel Development & Test System-integrated Modular Advanced ReacTor 18

19 Partnership for the Project KAERI KEPCO Consortium KEPCO Consortium Project Management, Funding, Marketing Leads the feasibility study on the construction of a FOAKE plant site survey, social acceptance, economics, etc System-integrated Modular Advanced ReacTor 19

20 Project Organization Government KAERI KEPCO Consortium Project Manage. Technology Validation Standard Design NSSS Design Fuel Design BOP Design Comp. Design Technology Validation : $60M Standard Design : $85M System-integrated Modular Advanced ReacTor 20

21 Project Milestone Technology Validation & Standard Design Approval ~17 Technology Validation Standard Design Separate Effect Tests Design Tools & Methods Integral Effect Tests (VISTA) Licensing Support Key Safety & Performance Validation Standard Design, Licensing Q&A SSAR, CDM, EOG Licensing Pre-Application Review Regulatory Review Pre-Application SDA Application Standard Design Approval FOAKE Plant Construction - ITL Integral System Confirmation Tests Plan Preparation Underway Construction System-integrated Modular Advanced ReacTor 21

22 Current Status Technology Validation 20 separate effect tests completed Integral effect tests : small scale SBLOCA tests completed Standard Design CDM, SSAR, EOG and related documents are submitted for the application of Standard Design Approval Licensing process is underway by Korean regulatory body System-integrated Modular Advanced ReacTor 22

23 Licensing Milestone toward SDA Pre-Application Review by KINS (in 2010) Application of Standard Design Approval (Dec. 30, 2010) Submits CDM, SSAR, EOG and related documents Submits 22 Technical Reports Document Conformance Evaluation (Feb. 2011) 190 comments demanding supplementary / additional materials 1 st Round Questionnaire (April 25, 2011) 932 questionnaires received 2 nd Round Questionnaire (July 25, 2011) (? ) questionnaires and pending issues Nuclear Safety Committee Review : Nov (goal) Standard Design Approval : Dec System-integrated Modular Advanced ReacTor 23

24 Contents Features of Current Status of Project The Safety of Perspectives and Closing Remarks System-integrated Modular Advanced ReacTor 24

25 , a Proven Technology basically adopts Proven Technologies of Existing PWR -specific Technologies are being fully Validated Experimental Validation of -specific Design Performance and Safety Total of 22 Validation Experiments were Selected based on PIRT (Phenomena Identification and Ranking Table) Experts Opinions from Regulation, Industries, Institutes and Universities Experimental Validation envelop Fuel/Core, TH/Safety, Mechanics/Components and Digital I&C Software Validation of Key Design Tools and Methods Core Physics, Core Thermal-Hydraulics, Safety Analysis,. System-integrated Modular Advanced ReacTor 25

26 Technology Validation Tasks 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 -ITL Digital MMIS Safety System 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 Control Room MMI Human Interface Control Room FSDM Design Data Standard SAR Standard Design Approval System-integrated Modular Advanced ReacTor 26

27 Safety Goal of Core Damage Factor Goal (Internal Event) less than 10-6 / RY Containment Failure Factor Goal less than 10-7 /RY Operator Action Spare Time at least 30 min. Capacity for Station Black-Out minimum 8 hours Severe Accident Mitigation Design Earthquake Design 0.3g System-integrated Modular Advanced ReacTor 27

28 Safety Systems of Passive Residual Heat Removal System (4 trains) Safety Injection System (4 trains) Shutdown Cooling System (2 trains) Containment Spray System Diesel Generator Alternate AC Hydrogen Control Passive auto-catalyst recombiner Counter Measure Severe Accident Large inventory of reactor coolant Large containment volume System-integrated Modular Advanced ReacTor 28

29 Evaluation for Station Blackout Safety is secured against Station Blackout 2 x Water-tight EDG and AAC insures Emergency Power Supply If EDG/AAC fails, Fully Passive (No Electricity) PRHRS insures Safe Shutdown (PRHRS Heat Sink can be Replenished) Even with Incredible EDG/AAC+PRHRS failure, Sufficient Grace Time* is insured for Operator s Mitigation Actions : Probability of Event Occurrence for multiple failures of EDG/AAC+PRHRS = ~ /RY PAR passively removes Hydrogen in Containment, if any Scenario EDG/AAC PRHRS Grace Time * 1 Yes All 4 Trains - 2 No All 4 Trains 20 Days** 3 No 2 Trains 10 Days** 4 No No 2.6 Days * Grace Time is defined as the Time allowed for Operator s Action before Core Damage ** No Replenishment of PRHRS Heat Sink Assumed System-integrated Modular Advanced ReacTor 29

30 Contents Features of Current Status of Project The Safety of Perspectives and Closing Remarks System-integrated Modular Advanced ReacTor 30

31 Perspectives of -SDA Project Certified Design will be available by 2012 for commercial deployment is a Viable Option for Early Deployment of SMR Enhanced safety and operability by advanced design features Economic feasibility Flexible applications for both electricity and heat supply Low licensing risks by use of proven and fully validated technologies KEPCO consortium with wide NPP experiences strengthens the viability of Technology Innovation will continue Aircraft Crash : Underground Containment Multi-Unit Modularization Full Passive Safety Systems : Primary System System-integrated Modular Advanced ReacTor 31

32 Perspectives of Footprint 300 x 300 m for Electricity System 200 x 300 m for Desalination System Construction Period 3 years Target Economics Construction Cost : $5,800/kWe Levelized Generation Cost : ~ 6.1 /kwh System-integrated Modular Advanced ReacTor 32

33 Total Solution Provider Design Team Technology Provider KAERI/KEPCO E&C / KEPCO NF /DOOSAN KEPCO Consortium Project Management Marketing, Financing Brand Power Team will contribute to the Smarter World System-integrated Modular Advanced ReacTor 33

34 Thanks for your attention! System-integrated Modular Advanced ReacTor 34