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Archivio digitale delle tesi discusse presso l’Università di Pisa

Tesi etd-02022026-172438


Tipo di tesi
Tesi di laurea magistrale
Autore
NUCCILLI, ALESSANDRO
URN
etd-02022026-172438
Titolo
Methodology for Neutronic Safety Assessment of a VVER-1000/V-320 Fuel Cycle
Dipartimento
INGEGNERIA CIVILE E INDUSTRIALE
Corso di studi
INGEGNERIA NUCLEARE
Relatori
relatore Giusti, Valerio
correlatore Ing. Dambrosio, Antonio
correlatore Ing. Mazzini, Guido
Parole chiave
  • ANDREA nodal diffusion code
  • conservative deterministic analysis
  • cross-section library validation
  • depletion and burnup calculations
  • HFP and HZP core states
  • kinetic parameters and β_eff
  • licensing support
  • Neutronic safety assessment
  • reactivity coefficients
  • reflector modeling
  • rod insertion limits verification
  • shutdown margin evaluation
  • three-dimensional power distribution
  • VVER-1000/V-320
  • xenon and samarium effects
Data inizio appello
20/02/2026
Consultabilità
Non consultabile
Data di rilascio
20/02/2096
Riassunto (Inglese)
Riassunto (Italiano)
This Master’s thesis develops a neutronic safety assessment for a VVER-1000/V-320 reactor over a full fuel cycle, verifying power distribution, reactivity feedbacks, shutdown capability and key kinetic parameters under penalizing conditions. A full-core 3-D model is built in the ANDREA nodal diffusion code on a 163-assembly hexagonal lattice, avoiding symmetry reductions to retain effects of non-uniform burnup, control-rod patterns and xenon redistribution. Radial/axial reflectors and an axial mesh tailored to safety-relevant peaks are explicitly represented, and depletion calculations track isotopic evolution and its impact on flux and power. The verification approach uses a matrix of core states and limiting scenarios spanning HFP and HZP, rod configurations (ARO, RIL, ARI, ARI-1) and xenon conditions from equilibrium to near-zero, evaluated at BOC, MOC, EOC and extended EOC. The study monitors radial/axial peaking, fuel–coolant interaction indicators, and kinetics—especially β_eff versus burnup—providing a consistent characterization of core behaviour and a basis for subsequent safety analyses.
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