Technical Program

PLENARY SESSIONS
  • BEPU Methodologies: Historical Remarks and Regulatory Requirements
    • Deterministic Safety Analysis for Nuclear Power Plants: IAEA Strategy and Approach, G. Rzentkowski (IAEA, Austria)
    • Historical Perspective of BEPU Methods,
      H. Glaeser (Consultant, Germany)
  • BEPU Methodologies and V&V Process
    • Scaling Issue and BEPU, Milorad Dzodzo (Westinghouse, USA)
    • On the Scalability of Validation Data for BEPU Analysis,
      Chul-Hwa Song (KAERI, Sud Corea)
  • BEPU in Thermal-Hydraulics: Current issues, Challenges and Future Perspectives
    • Uncertainty Quantification and Propagation in Core Thermal-hydraulics Sub-Channel Modeling and Simulation,
      Maria Avramova (NCSU, USA)
  • BEPU Methods and Results for GEN-IV & Other New Designs
    • Uncertainty analysis and modeling for HTGR,
      Gerhard Strydom (INL,USA)
PANEL DISCUSSION SESSIONS
  • 3D Challenges for TH System Codes
      Christophe Herer (IRSN,France) - Moderator
      A. Bousbia (BELV,Belgio)
      V. Parrinello (NINE,Italy)
      P. Fillon (CEA,France)
      S. Krepel (USNRC,USA)
  • SAPIUM - Good Practices for Thermal Hydraulic Codes Model Input Uncertainty Quantification
      J. Baccou (IRSN,France) - Moderator
      J. Zhang (Tractebel,Belgium) - Moderator
      P. Fillion (CEA,France)
      A. Petruzzi (NINE,Italy)
      R. Mendizábal (CSN,Spain)
      T. Skorek (GRS,France)
  • Validation Guidance and Needs
      E. Ivanov (IRSN) - Moderator
      T. Valentine (ORNL,USA)
      K. Ivanov (NCSU,USA)
      A. Petruzzi (NINE,Italy)
      U. Rohatgi (BNL,USA)
  • Development of BEPU for Supporting Industry and Utilities
      C. Frepoli (FPoliSolutions,USA) - Moderator
      A. Petruzzi (NINE,Italy)
      C. Delfino (Kairos,USA)
  • BEPU and Severe Accidents
      L.Herranz (CIEMAT, Spain) - Moderator
CONFERENCE SESSIONS & KEYNOTES
  • A.    BEPU METHODOLOGY: TECHNICAL
           AND REGULATORY REQUIREMENTS
    • A1. Licensing and Regulatory Requirements for BEPU
    • A2. V&V and BEPU
    • A3. Scaling Issue and BEPU
    • A4. Experimental Measurement Uncertainties and BEPU

  • B.    BEPU METHODOLOGIES DEVELOPMENT
    • B1. Statistical Methods for BEPU Analysis
    • B2. Bayesian Methods for BEPU Analysis
    • B3. Hybrid Methods for BEPU Analysis
    • B4. Sensitivity Methods as supporting tools for BEPU Analysis
    • B5. Methods for Quantification of Input Uncertainty Parameters

  • C.    BEPU FOR MULTIPHYSICS AND MULTISCALE APPLICATIONS
    • C1. Thermal-Hydraulics (including I&C simulators) and Reactor Physics
    • C2. Reactor Physics and Fuel Performance
    • C3. Thermal-Hydraulics, Reactor Physics and Fuel Performance
    • C4. Role of CFD and/or Structural Mechanics for MP&MS BEPU
    • C5. BEPU Challenges for MP&MS Applications including Numerical Issues
    • C6. Best-Estimate and Uncertainty Evaluation for Design Extension Condition (DEC) including Severe Accidents

  • D.    BEPU APPLICATIONS IN SAFETY ANALYSIS
           AND LICENSING FRAMEWORK
    • D1. Light Water Reactors (PWR, WWER and BWR)
    • D2. Heavy Water Reactors (CANDU, PHWR)
    • D3. Small Modular Reactors
    • D4.Priorities for BEPU Deployment for Current Plant Operation and Licensing Applications

  • E.    OTHER BEPU APPLICATION RESULTS
    • E1. BEPU Applications for Single Physics - Thermal-hydraulics
    • E2. BEPU Applications for Single Physics - Reactor Physics
    • E3. BEPU Applications for Single Physics - Fuel Performance
    • E4. BEPU Methods and Results for Passive System Applications
    • E5. BEPU Methods and Results for GEN-IV & Other New Designs
    • E6. BEPU Methods and Results for Design Extension Conditions
    • E7. BEPU Methods and Results for Research Reactor
    • E8. BEPU Methods and Results for Simulator Applications

  • F.    RECOMMENDATIONS AND FINDINGS FOR
           DEVELOPING FUTURE BEPU METHODOLOGIES
    • F1. International Program Findings and Recommendations for BEPU
    • F2. BEPU Requirements from Multi-physics and Multi-scale Simulations
    • F3. Demonstration of Practical Elimination of Accident Consequences
    • F4. Reactor Safety Margins Assessment for External Hazards
    • F5. Methods for Uncertainty Quantification in Non-Nuclear Disciplines

Technical Program Under Finalization

BEST ESTIMATE CONFERENCE HISTORY


2000 BEST ESTIMATE Washington DC USA
2004 BEST ESTIMATE Washington DC USA
2018 BEPU 2018 Lucca ITALY