Verification and Validation of DYN3D

Comparison with benchmark exercises:

  • Steady-state 3D IAEA benchmark (Report FZR-195)
 
  • AER benchmarks for VVER Reactors
 
  • Burn-up calculation for NPP Paks
 
  • AER benchmarks on control rod ejections and boron dilution transients in VVER-440
 
  • NEA-CRP benchmarks on control rod ejection and withdrawal in a standard PWR and NEA-NSC benchmarks on withdrawal of control rod in a PWR (Report FZR-195)
  •  Benchmark exercises for verification of the European code platform NURESIM
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  • OECD MOX RIA Benchmark on validation of multi-group transport approach 
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Comparison of DYN3D results with reference solution for the NEA-NSC benchmark - Case D:


 
Uncontrolled withdrawal of control rods at hot zero power: 
Nuclear power versus time
Hot pellet fuel enthalpy 
versus time
  • OECD Main Steam Line Break (MSLB) Benchmark:
Break of main steam line with shut down of the reactor. One stuck rod assumed. Consideration of  reduced efficiency of control rods in exercise 2 leads to recriticality. DYN3D result for nuclear power:


Maximum linear rod power of fuel assemblies:
Initial state  After shut down  At the moment of recriticality 

Comparison with measurements:

  • Kinetic experiments at the zero power reactor LR-0 (Czech Republic)
 
  • Comparisons of the fuel rod model with experiments simulating conditions of reactivity initiated accidents (RIA)
  • VVER-440 and VVER-1000 steady-state measurements
  • Critical boron con-centration
 
  • Control rod efficiency
 
  • Reactivity coefficients
 
  • Kinetics and steady-state neutron flux measurements at the V-1000 test facility (EU project VALCO)