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Extension, validation, and optimization of Serpent/DYN3D/ATHLET code system for SFR applications

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Extension, validation, and optimization of Serpent/DYN3D/ATHLET code system for SFR applications

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Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test

Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments

Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors

Nuclear Energy in Europe: Uranium Flow Modeling and Fuel Cycle Scenario Trade-Offs from a Sustainability Perspective

Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions

Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR)

TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions

Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor

Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor