{"id":161,"date":"2024-07-16T18:20:06","date_gmt":"2024-07-16T16:20:06","guid":{"rendered":"https:\/\/people.unipi.it\/valerio_giusti\/?page_id=161"},"modified":"2025-03-25T14:37:00","modified_gmt":"2025-03-25T13:37:00","slug":"masters-thesis-in-collaboration-with-n-in-e-nuclear-and-industrial-engineering","status":"publish","type":"page","link":"https:\/\/people.unipi.it\/valerio_giusti\/masters-thesis-topics\/masters-thesis-in-collaboration-with-n-in-e-nuclear-and-industrial-engineering\/","title":{"rendered":"Master’s Thesis in collaboration with N.IN.E. – Nuclear and Industrial Engineering"},"content":{"rendered":"\n

Topic I: CEFR coordinated research project<\/strong><\/p>\n\n\n\n

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The proposed Thesis work is in the framework of the IAEA Coordinated Research Project (CRP): \u201cNeutronics Benchmark of CEFR Start-Up Tests\u201d.
The Coordinated Research Project (CRP) will focus on neutronics benchmark analysis of the physics start-up tests performed at the China Experimental Fast Reactor (CEFR) in 2010-2011.<\/p>\n<\/div>\n\n\n\n

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CEFR is a small-size sodium-cooled fast reactor with a high neutron leakage core fuelled with uranium oxide and stainless-steel radial reflector.
Benchmark analysis of CEFR physics start-up tests will include evaluation of the criticality, control rod worth, reactivity effects, and neutron spectral characteristics. The recorded experimental data from the CEFR start-up will provide an excellent opportunity to validate the physical models and neutronic simulation codes.
The activities of the CRP have been performed in collaboration between NINE and UNIPI. A benchmark extension has been proposed including the following aspects:
\u2022 Burn-up
\u2022 Deep penetration
\u2022 Neutron dynamics
\u2022 Neutron Spectrum
\u2022 Group Constants
\u2022 Kinetic Parameters
\u2022 Reactivity distribution<\/p>\n\n\n\n

Possible thesis activities<\/strong><\/p>\n\n\n\n

The activities to be performed will be related to the benchmark participation. In particular, the input developed in the Serpent 2 code will be provided. It has to be adapted to the analysis of the new work packages. Results will be compared with other participants and experimental data (when available).<\/p>\n\n\n\n

Topic II: Rostov-2 VVER-1000 benchmark<\/strong><\/p>\n\n\n\n

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The Rostov-2 VVER-1000 benchmark tests the capabilities of 3D multi-physics reactor simulation codes to analyze complex transients with coupled core-plant interactions and complicated fluid mixing phenomena. The benchmark aims to compare the performance of traditional multi-physics codes and novel high-fidelity multi-physics code systems and methods and to provide recommendations on the advantages and disadvantages of standard and novel approaches.<\/p>\n<\/div>\n\n\n\n

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Several tests with well-documented neutronics and thermal-hydraulics measurement data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The benchmark team selected a test (transient), which allows validation of novel high-fidelity multi-physics codes. Differently from all previous multi-physics OECD\/NEA benchmarks for coupled code validation, implementing high-fidelity multi-physics simulation codes could allow predicting pin-by-pin power distributions and flow mixing in the reactor pressure vessel including its active core part.<\/p>\n\n\n\n

The Rostov-2 VVER-1000 benchmark has two phases with a suite of sequential exercises. The first phase is designed to provide the framework to assess the ability of the standard multi-physics (coupled system thermal-hydraulic (TH)\/neutronics (N)) codes to predict the transient response of the power plant at an assembly-wise level. Thus, an assembly-wise homogenization of thermal-hydraulics and neutron physics parameters will be applied. The second phase of the benchmark is still under development.<\/p>\n\n\n\n

Possible thesis activities<\/strong><\/p>\n\n\n\n

Based on previous works that concerned the development of a cross-section database and a preliminary PARCS model of the Rostov-2 core, the current activities will include participation at the benchmark with the Phase I Exercise 2 – Coupled 3-D neutronics\/core thermal-hydraulic response evaluation. The purpose of this exercise is to model the reactor pressure vessel with the active core only. Inlet and outlet core transient boundary conditions are provided by the benchmark team, based on calculations performed with coupled system code or applying any information directly from the measured data. Simulation of the hot zero power (HZP) state of the reactor core (Exercise I-2a) is part of this exercise to test the neutronics model including the cross-section library. Exercise I-2b includes calculations of initial hot power (HP) steady-state conditions and the transient test scenario simulation. The required two-group assembly-wise homogenized cross-section library is provided in electronic format. In case of interest, the participants can generate their own two-group assembly-wise homogenized cross-section library.<\/p>\n\n\n\n

In particular:<\/p>\n\n\n\n