Abrupt collapse of vapour bubbles at high Jakob number is the leading physical phenomenon of the simulated chugging sodium boiling regime occurring during unprotected loss of flow (ULOF) accident in Sodium Fast Reactor (SFR) low-void core designs. The ESFR-SMART Horizon 2020 project aims at a better understanding and simulation of chugging conditions. Therefore, the small-scale two-phase flow facility “CHUG” for the mock-up of sodium boiling using water as sodium simulant has been designed at Paul Scherrer Institut (PSI) and built at the Laboratory of Reactor Systems behaviour at EPF Lausanne. CHUG consists of an acrylic glass test section filled with water at ambient temperature and atmospheric pressure, where high-temperature steam is inj...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
In this paper, a numerical investigation of the hydrodynamic characteristics of Taylor bubbles (T-B)...
International audienceThe phenomenology of coolant boiling in the core of a Gen IV Sodium Cooled Fas...
One of the main aims of ESFR-SMART European project is the safety evaluation of a low-void Sodium Fa...
Chugging of steam direct contact condensation is a well-known phenomenon and one of the most studied...
Unstable direct contact condensation called ``Chugging'’ that occurs in certain conditions in the pr...
This work deal with the analysis of phenomena of sharp vaporization that may occur in the presence o...
Calculational analysis of the unprotected loss of flow (ULOF) accident in a Generation-IV SFR, featu...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
Condensation, of steam bubbles generated at an orifice and rising freely through water, subcooled fr...
International audienceAbstract The computational codes used in the evaluation of the European sodium...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
The AP1000® advanced reactor passive safety systems are based on natural phenomena to ensure the con...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
In this paper, a numerical investigation of the hydrodynamic characteristics of Taylor bubbles (T-B)...
International audienceThe phenomenology of coolant boiling in the core of a Gen IV Sodium Cooled Fas...
One of the main aims of ESFR-SMART European project is the safety evaluation of a low-void Sodium Fa...
Chugging of steam direct contact condensation is a well-known phenomenon and one of the most studied...
Unstable direct contact condensation called ``Chugging'’ that occurs in certain conditions in the pr...
This work deal with the analysis of phenomena of sharp vaporization that may occur in the presence o...
Calculational analysis of the unprotected loss of flow (ULOF) accident in a Generation-IV SFR, featu...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
Condensation, of steam bubbles generated at an orifice and rising freely through water, subcooled fr...
International audienceAbstract The computational codes used in the evaluation of the European sodium...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
The AP1000® advanced reactor passive safety systems are based on natural phenomena to ensure the con...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
In this paper, a numerical investigation of the hydrodynamic characteristics of Taylor bubbles (T-B)...
International audienceThe phenomenology of coolant boiling in the core of a Gen IV Sodium Cooled Fas...