Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test
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Gas cooling in nuclear power plants (NPPs) has a long history, the corresponding reactor types developed in France, the UK and the US having been thermal neutron-spectrum systems using graphite as the moderator. The majority of NPPs worldwide, however, are ...
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Four sets of experimental data (total of 658 data points) for heat transfer to liquid metals (NaK of different compositions and Hg) flowing in a triangular or square lattice of cylindrical rods with pitch-to-diameter ratios of 1.1 up to 1.95 for a wide ran ...
Decay heat removal is a key safety and design issue for the Generation IV gas (helium)-cooled fast reactor. This paper investigates the natural convection capability of the dedicated DHR loops under depressurized conditions while injecting a heavy gas into ...
During the past ten years, different independent factors, such as the rapidly increasing worldwide demand in energy, societal concerns about greenhouse gas emissions, and the high and volatile prices for fossil fuels, have contributed to the renewed intere ...
The Paul Scherrer Institute used to be very active in fuel fabrication R and D using the internal gelation process, which is a promising production method for spherical nuclear fuel. Such fuel kernels can be directly packed in a cylindrical cladding (a sph ...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicab ...
The reference fuel design currently being considered within the Generation-IV Gas-cooled Fast Reactor (GFR) project is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinders. The fuel is mixed plutonium-uranium carbide, whi ...
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