Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments
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This dissertation covers both experimental and numerical neutronics studies to evaluate
the adequacy of the Serpent/PARCS code sequence for modeling the steady-state and
kinetics behavior of the CROCUS reactor. The reactor presents design characteristics
t ...
The analysis of nuclear reactors for performance and safety assessment benefits from the use of computational tools. In this context, this work aims at the development and application of a thermal-hydraulics methodology and related software that respond to ...
New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast ne ...
DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safety analyses of Sodium cooled Fast Reactors (SFRs) at the Helmholtz-Zentrum Dresden-Rossendorf. This thesis focuses on the first stage of the development pro ...
The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by de ...
