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Archivio digitale delle tesi discusse presso l’Università di Pisa

Tesi etd-04112021-061310


Tipo di tesi
Tesi di laurea magistrale
Autore
MOHAMED, AHMED ABDELRAHMAN MOHAMED ABDELMAGED
Indirizzo email
a.abdelrahmanmoha@studenti.unipi.it, a.a.shamikh@gmail.com
URN
etd-04112021-061310
Titolo
Validation of the thermal-Hydraulic Subchannel code COBRA-TF
Dipartimento
INGEGNERIA CIVILE E INDUSTRIALE
Corso di studi
INGEGNERIA NUCLEARE
Relatori
relatore Prof. Ambrosini, Walter
relatore Prof. Giusti, Valerio
relatore Dott. Petruzzi, Alessandro
Parole chiave
  • Nuclear
  • Subchannel CODE
  • Thermal-Hydraulic
Data inizio appello
26/04/2021
Consultabilità
Non consultabile
Data di rilascio
26/04/2091
Riassunto
CTF is the version of the thermal-hydraulic sub-channel code COBRA-TF (Coolant-Boiling in Rod Arrays-Two Fluids), designed for Light Water Reactor (LWR) analysis. It uses a two-fluid, three-field representation of two-phase flow, which makes the code capable of modeling two-phase flow in Boiling Water Reactors (BWR) during nominal operating conditions.
CTF has been subjected to a strict verification procedure, by addressing the mathematical accuracy of the numerical solutions on multiple stages. The code was then validated using numerous experimental databases, including the U.S. Nuclear Regulatory Commission (NRC) / Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA-OECD) Boiling Water Reactor Full Bundle Tests (BFBT) Benchmark.
This degree thesis work is devoted to a further assessment of the CTF Code in comparison with experimental data from the BTBT, aiming for best- estimate evaluations of the nuclear reactor safety margins.
The BFBT benchmark contains a large amount of test cases representative of BWRs steady-state and off-nominal operating conditions, which makes it one of the most widely used benchmark for validating BWR modeling tools. One of the main experimental tests involve void distribution tests. Specific experimental cases were chosen and simulated using CTF. Statistical studies were carried out on the void distribution cases to evaluate the code modeling uncertainties.
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