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Bringing Engineering Analysis Codes Into Real-Time Full-Scope Simulators
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Bringing Engineering Analysis Codes Into Real-Time Full-Scope Simulators


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Presented at the 2013 Nuclear Simulation and Training China Forum in Beijing. For more information on GSE's real-time simulators and engineering capabilities, go to, follow GSE on Twitter …

Presented at the 2013 Nuclear Simulation and Training China Forum in Beijing. For more information on GSE's real-time simulators and engineering capabilities, go to, follow GSE on Twitter @GSESystems and connect on

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  • A popular term for describing the new role of the simulator is Simulator Assisted EngineeringFor many of these new plants, the simulator is their first view of the plant running. It provides an Integrated Environment testing out design assumptions.For years simulators have been used to test the DCS implementation in non-nuclear applications, finding issues with control strategies as well as bugs in implementing the DCS when it is less costly to fix.From a human factors perspective, operating a nuclear plant almost totally from computer screens versus panel boards is a “radical” change. Presenting the right level of information, determining the navigation and conduct of operations, and testing out new operator aids such as electronic procedures and alarm handling systems are all effective uses of the simulator.For many of the new plants, operating procedures just don’t exist and the simulator is a perfect tool for developing the procedures and corresponding training materialsFinally at the end of the day, you also have your ANS 3.5 simulator available for use in licensing operators
  • SimultaneouslyCompare current trending with reference data.Statistical built-in functions to evaluate code performance, such as sensitivity & uncertainty study.Give insight to code users.Simultaneous code performance, do not need to wait until code to be terminated to know how code performs comparing with reference data.
  • demo case was applied to both desktop psa-hd & full-scope simulator PSA-HD.Desktop PSA-HD does not include S3R & BOP. Has successfully run the different transient for 32 hours.Full-scope PSA-HD has interfaces built-in and integrated with full-scope simulator. Has successfully run LOCA for more than 8 hours.
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    • 1. Bringing Engineering Analysis Codes Into Real-Time Full-Scope Simulators
    • 2. Outline I. Full-scope simulator evolution II. High-definition simulator platform III. MAAP in full-scope simulators IV. Support integrated training of NOP, EOP and SAMGs 2
    • 3. Real-Time Simulator • Real-time simulators came to the nuclear industry as training tools in the 1970s – Full plant modeled, but models often “hand crafted” – Analog controls, traditional hard-panel control panels • Today’s nuclear power plant simulator is high fidelity – Same scope, but – High-definition predictive models used to model plant systems – Digital controls and modern HSIs: detailed view of systems • Today the real-time simulator is an engineering tool – Holistic dynamic plant model 3
    • 4. Real-Time Simulator • Broad or full-scope plant model – Includes primary, secondary, BOP and safety system and at least a high-fidelity main loop • All models integrated and synchronized (coupling) • One second of problem time = One second of real time (feels like the real plant) • Models are interactive – Observe and operate like the real plant – Can be integrated with real control systems 4
    • 5. New Missions of Simulator • Holistic engineering V&V platform − Validation of system design issue in integrated “plant” • Controls system design and V&V − Validation and refinement of logic and controls strategies as a development tool for new control strategies • Human factors engineering platform − Support design of DCS interface, alarms, procedures, etc. − Support design of digital control rooms and information layout − Demonstrate viability of these designs to regulator • Develop and validate operating procedures • Address post-Fukushima challenges 5
    • 6. GSE High-Definition (HD) Platform • Running third-party best estimate or safety analysis codes as integral parts of full-scope simulators • Enforce synchronization between multiple systems through client and server architecture • Maintain integrity of original code • Ensure repeatability • Allow users to have access to model internal memory and variables • Advanced 2D & 3D visualization interfaces 6
    • 7. GSE HD Platform Architecture Client Customized plug-in interface client Standard HD server configuration Simulator Host Executive (GSE or non-GSE) HD Client Executive #1 Input Server Output Client C module Control Status request Server input/output 7
    • 8. Multiple HD Servers BWR Configuration • • HD Server #1 Simulator Server #1 (CPU #1): RELAP for BWR vessel (GSE or other) Server #2 (CPU #2): Neutron Kinetics Code (ex. REMARK) HD Server #2 HD Client PWR Configuration • • • Server #1 (CPU #1): RELAP for primary loops HD Server #3 HD Server #4 SMR Configuration Server #2 (CPU #2): RELAP for steam generators • Server #1 (CPU #1): RELAP for module #1 Server #3 (CPU #3) Neutron kinetics code (ex. REMARK) • Server #2 (CPU #2): RELAP for module #2 • Server #3 (CPU #3): S3R for module #1 • Server #4 (CPU #4): S3R for module #2 8
    • 9. Data-Centric System MAAP MAAP 4.06 MAAP 4.08 MAAP 5.01 MAAP 5.02 MAAP 5.03 RELAP5 -3D 9
    • 10. Graphical SAMGs Computer-based procedures that help automate the SAMG control the sequence of events in PSA-HD simulation 10
    • 11. V&V Tool reference data simulator data 11
    • 12. Extensible Platform • Servers may include GSE or third-party models, such as: − GSE’s Topmeret, REMARK − MAAP5, MAAP4 − INL’s RELAP5-3D v2.4 & v4.0 − Studsvik’s S3R (neutronics) and thermal margin codes − MELCOR − SPICE – analog circuit board − Russian VVER Neutronic modes • Flexible configuration − Multiple computers − Multiple processors/cores − Varied frame rates 12
    • 13. RELAP5-HD Installations Reactor Type BWR, GE PWR, WE PWR, WE PWR, WE Small Modular Reactor, B&W PWR, WE CANDU PWR, RUS Naval Reactor PWR, WE BWR, GE Small Modular Reactor, NuScale Country Status Japan United States United States United States United States On-going On-going On-going On-going On-going United States Canada Ukraine UK Netherlands United States United States On-going On-going On-going On-going On-going RFT RFT RELAP5-3D requires US DOE export license Reactor Type PWR, WE PWR, WE PWR, CE PWR, WE PWR, ASEA PWR, ASEA BWR, ASEA PWR, ASEA BWR, ASEA BWR, ASEA BWR, ABB BWR, GE PWR, RUS PWR, RUS JMTR PWR, WE BWR, GE Country South Korea South Korea South Korea South Korea Germany Germany Germany Germany Sweden Sweden Sweden Switzerland Bulgaria Ukraine Japan Japan Japan Status RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT 13
    • 14. MAAP4 & 5 Installations Reactor Type BWR, GE Plants, Country K5, Japan 3-Loop PWR, WE 4-Loop PWR, WE (ice condenser) BWR, GE KTN2, Japan KON1, Japan BWR, GE BWR, GE 2F2, Japan TS1, Japan (Same design as 1F1) TS2, Japan 4-Loop, PWR, Mitsubishi PWR, WE PWR, WE PWR, WE BWR, ASEA TK2, Japan Status MAAP 3.0, 1994 MAAP 4.0, 2013 MAAP4, 2006 MAAP4, 2006 MAAP 3.0, 1998 MAAP 4.0, 2013 MAAP3, 2001 MAAP3, 1997 R2, Sweden United States United States MAAP 3.0, 1998 MAAP 4.0, 2013 MAAP5, on-going MAAP5, on-going MAAP5, on-going Sweden MAAP5, on-going MAAP code requires US EPRI user license 14
    • 15. GSE First-of-a-Kind Engineering Simulator Experience Westinghouse AP1000 NuScale Power Pebble Bed Modular Reactor HYH CPR-1000 HFE and Control V&V Platform Ultra Supercritical Korea IGCC China SMART Korea Atomic Energy Research Institute B&W mPower Engineering and HFE Simulator 15
    • 16. HD Interfaces • • • • • • • • • • Interface functions BOP to HD fluid interface (BOP calculates flows) BOP to HD fluid interface (HD calculates flows) HD to HD fluid interface (typically only used for U-tube rupture) BOP to HD heat structure interface Standard interfaces HD to HD heat structure interface and automated Core model interface generation Miscellaneous control interface Instrumentation interface Remote function / Fast time interfaces 16
    • 17. MAAP5 in Full-Scope Simulator Electrical System JElectric I&C JControl Ex-plant DOSE Simulation MAAP5 In-plant DOSE simulation In-plant DOSE simulation Unit 2 Containment MAAP5 Unit 1 Containment MAAP5 SG TH Code/ MAAP5 RCS TH Code/ MAAP5 Core S3R Auxiliary Building MAAP5 Spent Fuel Pool BOP JTopMeret RCS TH Code/ MAAP5 SG TH Code/ MAAP5 Core S3R 2-Unit Westinghouse 4-Loop PWR 17
    • 18. MAAP5 in Full-Scope Simulator 0 Min. ~60 Min. 3 Hrs. 20 Min. 5 Hrs. 30 Min. Scenario Steady-state LOCA, code transition LOCA, Core melt-down LOCA, Vessel failed Unit #1 RCS/SG TH Code Timeline MAAP Server #1 Transition MAAP5.0 Shared Aux. Building (w/ SFP) MAAP5.0 BOP MAAP Server #2 Unit #1 Containment MAAP5.0 GSE JTopmeret Simulator Neutronics Studsvik S3R MAAP5.0 18
    • 19. A More Reliable Engineering Code Accumulation of Benchmarks NQA (Future) Documentation Best Estimate Core Code Code Improvement Verification & Validation New Capabilities 19
    • 20. Engineering Codes to Simulator Training Simulator Simulator System Dev. & Test Process Engineering Codes All Simulato r System Models Benchmarks Eng. Code Simulation System System Configuration Eng. Code Input Deck Various Interfaces NQA (Future) Documentation Code Improvement V&V New Capabilities 20
    • 21. Progressive Simulator Solutions HD (MAAP, RELAP, JADE, etc..) Desktop HD (MAAP or RELAP) Fullscope simulator Desktop simulator Riskinformed simulator HD (MAAP, RELAP, JADE, uncertainty, database, etc..) 21
    • 22. Integrated EOPs, SAMGs, etc. NOPs EOPs SAMGs Postulated Actions Exercises Full-scope Simulator (RELAP5-HD) Realistic Training Main Control Room Local Field Personnel Expanded Training Technical Support Center Radiological Center Emergency Director (Plant Manager) 22
    • 23. Next-Generation Simulation Multi-scale, multi-physics modeling Wide-scale data processing Large-scale numerical computation Multi-variant, multi‐response and multi-dimensional problems • Total data model integration • Data, computations, systems, uncertainty quantification and knowledge management • • • • 23
    • 24. EPRI MAAP Code • ''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program that performs severe accident analysis for nuclear power plants including assessments of core damage and radiological transport. A valid license to MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a customer being able to use MAAP 5.0 with [LICENSEE PRODUCT]. • EPRI ( conducts research and development relating to the generation, delivery and use of electricity for the benefit of the public. An independent, nonprofit organization, EPRI brings together its scientists and engineers as well as experts from academia and industry to help address challenges in electricity, including reliability, efficiency, health, safety and the environment. EPRI does not endorse products or services, and specifically does not endorse [NEW PRODUCT NAME] or GSE. Interested vendors may contact EPRI for a license to MAAP 5.0." 24
    • 25. GSE Systems, Inc. Thank you! 25
    • 26. For more information: Go to: Follow us on: Call: +1 800.638.7912 Twitter @GSESystems Email: