Platform for Multi-Unit Severe Accident Simulation


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This presentation explores the real-time simulator as a platform for severe accident simulation and how it can be used to address post-Fukushima challenges in the nuclear energy industry. Presented at ANS PSA International Topical Meeting. For more information, go to and follow GSE Systems on Twitter @GSESystems and Thanks for viewing!

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  • 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.
  • We developed a tool that amazingly describes industry events and used it effectively to describe the event at Fukushima. This tool, DesignEP, expertly describes the Fukushima event and has been used by ERIN and EPRI
  • Users can quickly visualize the status of the unit, including RCS and containment. Any internal variable can be accessed and graphed for in depth understanding
  • 3-D like modern GUI for PSA-HD. Much better illustration to the real nuclear plant condition. Details and scales are preserved to give correct impression to the operator & code users.
  • 3-D like modern GUI for PSA-HD. Much better illustration to the real nuclear plant condition. Details and scales are preserved to give correct impression to the operator & code users.
  • This is an example that how ex-plant dose could be displayed.Max 10 calculation points can be modeled in maap code.Plume dispersion in atmosphere can be modeled in maap.Rain, wind as well as building blocking can be taken into consideration.
  • Platform for Multi-Unit Severe Accident Simulation

    1. 1. Simulator Platform for Multi-Unit Severe Accident Simulation
    2. 2. Outlines • Real-time simulator • Post-Fukushima challenges • Simulator technology • Case studies for multi-unit plant site 2
    3. 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 NPP simulator is high-fidelity – – – – Same scope, but… Engineering-grade computer codes, such as RELAP, MAAP, S3R Digital controls and modern HSIs Holistic dynamic plant model: - Multi-physics, multi-systems, multi-codes, multi-units 3
    4. 4. Real-Time Simulator • Broad or full-scope plant model – Includes primary, secondary, safety systems, balance-of-plant, electrical systems, I&C, etc. – Normal operation, transients, design-basis accident • All models integrated and synchronized (coupling) • 1 second of problem time = 1 second of real time (feels like the real plant) • Models are interactive – Observed and operated like the real plant – Can be integrated with real control systems 4
    5. 5. Post-Fukushima New Recommendations & Requirements Beyond Design-Basis Multi-Unit Events, PRA Extended SBO FLEX New Mitigation Strategies Predictive Response 5
    6. 6. Simulator Technology for Resource Alignment • Common technology for: – – – – – – – Engineering Risk assessment Operations Training Emergency planning Local authorities and regulators Full-scope simulator for operator training 6
    7. 7. GSE High-Definition Platform • Running third-party best estimate analysis codes as integral parts of simulators • Enforce synchronization between multiple systems and human interactions • Maintain code integrity and repeatability • Have access to internal memory and variables • Advanced 2D, 3D visualization interfaces • Post-data processing tools with database • Multiple processors and computers 7
    8. 8. Parallel Architecture for MAAP and MELCOR JADE Operation Station DCS-Like HMI Animation, Soft Panels, Interface Simulation Control HD Server 8 for RASCAL, Site HD Server 1 for MAAP5, Unit 1 HD Server 2 for MAAP5, Unit 2 HD Server 3 for MAAP5, Unit 3 HD Client JADE Dashboard (JDB) HD server Graphical User Interface Interactive Control, Monitor, V&V HD Server 4 for MELCOR, Unit 1 HD Server 7 for MACCS2, Site HD Server 5 for MELCOR, Unit 2 HD Server 6 for MELCOR, Unit 3 8
    9. 9. Main Simulation Processes Start HD Executive Start 3rd Party Engineering Code Batch Job Read Input or Restart Decks Interactive simulations with MAAP and MELCOR in the same HD platform 3rd Party Engineering Code Input or Restart File Read Input or Restart Decks Initialize 3rd Party Engineering Code reset Run a Frame HD IC Files Interactive User Actions snap exit End Create restart or update input decks: PyGI Initialize 3rd Party Engineering Code Scheduled freeze Text Edit Output Run the Whole Job Scheduled Time end End 9
    10. 10. JADE DashBoard (JDB) Host and executive connection Executive control Listed output and command line Trending/Data Collection Executive modules 10
    11. 11. V&V Tool MAAP MELCOR Easy to compare MAAP and MELCOR results 11
    12. 12. Graphical SAMGs Computer-based procedures help automate the SAMG to control the sequence of events in PSA-HD simulation 12
    13. 13. Fukushima Multi-Unit Accidents • Used MAAP code as analytical and modeling tool • Developed in collaboration with EPRI and ERIN Engineering 13
    14. 14. Fukushima Unit 1 at 3H:38M & 11H:11M 14
    15. 15. Fukushima Unit 2 at 76H & 120H 15
    16. 16. Fukushima Unit 3 at 76H & 120H 16
    17. 17. PWR with 2 Units and Spent Fuel Ex-plant DOSE Simulation In-plant DOSE Simulation In-plant DOSE Simulation Unit 1 Containment Unit 2 Containment SG RCS Auxiliary Building RCS SG Spent Fuel Pool Core Core MAAP5 MAAP5 MAAP5 17
    18. 18. Loss of All AC Power with FLEX Pump Operation SG 1 SG 2 SG 4 SG 3 External Water Source s3.rar G FLEX Portable Diesel Generator 18
    19. 19. Loss of All AC Power – SG#1/3 Levels kept by FLEX pumps at 50M 19
    20. 20. Reactor Core at 3H:36M Time 3H:36M UNIT 1 UNIT 2 20
    21. 21. Unit 2 Containment & Flammability at 6H:23M Time 6H:23M:46S 21
    22. 22. Off-Site Radiological Dose at 6H:20M Time 6H:20M:45S 22
    23. 23. Integrated EOPs, SAMGs, etc. NOPs EOPs SAMGs Postulated Actions Realistic Training Local Field Personnel Other codes MAAP Full-scope Simulator (RELAP5-HD) Main Control Room Exercises Expanded Training Technical Support Center Radiological Center Emergency Director (Plant Manager) 23
    24. 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. 25. For more information: Go to: Follow us on: Call: 800.638.7912 Twitter @GSESystems Email: