Safety analysis of nuclear facilities

  • Rating modification influence on safety margins;
  • Validation of nuclear power plant simulator;
  • Supporting analysis of emergency procedures (EOP, SAMG);
  • change of power influence on safety margins;
  • evaluation of safety margins in reactor shut down state;
  • analysis of operational transients: cause, course and consequences;
  • support to PSA (Probabilistic Safety Assessment).

 

Enconent’s competence in the field of safety analysis of nuclear facilities:

  • simulation of transient phenomena, accidents and severe accidents in primary and secondary side and inside containment of nuclear power plant (RELAP, TRACE, RELAP/SCDAPSIM, MELCOR, GOTHIC, CONTEMPT, COBRA);
  • dynamic calculation of neutron flux in reactor core during operation and accidents (PARCS);
  • FEM stress analysis of piping and vessels;
  • Assessment of radiological consequences to the plant employees and the general population;
  • Using of coupled programs (RELAP5/PARCS, RELAP5/PARCS/COBRA, RELAP5/GOTHIC)

 

References (in collaboration with FER)

  • RELAP5/mod3.3 Analysis of RVHVS line break
  • Analysis of Manual Reactor Trip from 100 % Power (Cycle 23)
  • Closure of Both MSIV from Full Power Operation (Cycle 23)
  • Relap5/Mod3.3 Analysis of Partial and Total Loss of Reactor Coolant Flow (Cycle 23)
  • Relap5/Mod3.3 Steam Line Break Analysis (Cycle 23)
  • Relap5/Mod3.3 Analysis of Stuck Open PRZ PORV with Emergency Core Cooling System Inhibited (Cycle 23)
  • Development of the curriculum for safety assessment as a part of Safety Assessment Education and Training Programme, IAEA, 2008-2009
  • IAEA Co-ordinated Research Project (CRP) “Evaluation of Uncertainties in Best Estimate Analyses(J7.20.05)”, 2006-2009,
  • Relap5/Mod3.3 Analysis of Small Break LOCA during Mode 3 and Mode 4 Operation for NPP Krsko
  • RELAP5/mod3.3 Analysis of NSAL-06-015 Single Failure Scenario for NEK Steam Generator Tube Rupture (SGTR) (Support Analysis for Resolution of NSAL 06-15)
  • RELAP5/mod3.3 Analysis of NEK USAR scenario for Steam Generator Tube Rupture (SGTR)(Support Analysis for Resolution of NSAL 06-15)
  • Operating Limits and Procedures Review – Complementary EOP Verification on Specific Topics, FER-ZVNE/SA/DA-TR06/06-0, 19.07.2006
  • Preparation of the Draft Ordinances based on the Law on Nuclear Safety in Accordance with EU Directives and Standards IAEA, DZNS
  • Relap5/Mod3.3 Analysis of NPP Krsko Station Blackout Accident for fhe Modified WOG2000 RCP Seal Leakage Model Assumptions
  • Relap5/Mod3.3 Analysis of Influence of the Initial Condition Average Temperature on the Loss Of Load/Turbine Trip Analysis, (Response to NSAL-03-1)
  • Relap5/Mod3.3 Analysis of Influence of CVCSs Modeling on the Loss Of Offsite Power Accident, (Response to NSAL-00-013)
  • Best-Estimate Analysis In Support of Required Shutdown Conditions For Mod 4 (Plant Statuses 1 To 5)
  • Analysis of Ambient Conditions At IB Elevation 100.3 after Isolation of SG Blowdown Break
  • KFSS Stuck Open one PORV with ECCS Inhibited (Cycle 20)
  • KFSS SLB Inside CNT (Cycle 20)
  • KFSS Trip of Single and Both RCP (Cycle 20)
  • KFSS Closure of both MSIV (Cycle 20)
  • KFSS Rx Trip (Cycle 20)
  • Relap5/Mod3.2.2 Analysis of the RCP 2 Trip Plant Event
  • Analysis of the Scaled Loss of RHR Experiment Scenario
  • Calculation of Pressure and Temperature Environmental Conditions for NEK Rooms IB011, IB012, IB014 and IB015 Following SG Blowdown Line Break
  • Analysis of MSLB Spectrum Using Coupled Relap5/Mod3.2.2/Quabox
  • GOTHIC and RELAP5/MOD3.2.2 Analysis Of Loss of RHR During Shutdown
  • RELAP5/MOD3.2.2 Analysis of SBLOCA (1,2,3 and 8 in)
  • RELAP5/MOD3.2.2 Analysis of Stuck Open PRZ PORV with ECCS Inhibited
  • RELAP5/MOD3.2.2 Analysis of SLB Inside the Containment
  • RELAP5/MOD3.2.2 Analysis of Partial and Total Loss of Reactor Coolant Flow
  • RELAP5/MOD3.2.2 Analysis of Partial and Total Loss of MFW
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