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The GFR (Gas cooled Fast Reactor) combines the advantages of a fast neutron spectrum with those of high temperatures. Given the high core outlet temperatures exceeding 800 C, it is clear that conventional metallic core structures and fuel cladding will be ...
Until about the year 2030, current-day nuclear power plants (NPPs) will be replaced by so-called Gen-III or Gen-III+ units, which are mainly based on light water reactor technology. The principal new features are increased safety and improved economical ef ...
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 advanced fast reactors of the fourth generation should be capable to breed their own fuel from poorly fissile 238U and to recycle the actinides from their own spent fuel. However, this recycling or actually the closure of fuel cycle has negative impact ...
The improvement of the "radiological cleanliness" of nuclear energy is a primary goal in the development of advanced reactors and fuel cycles. The multiple recycling of actinides in advanced nuclear systems with fast neutron spectra represents a key option ...
In order to improve the purification capacity of an aerobic granular sludge, two aeration strategies were designed and tested. The goal was to optimize the nitrogen removal performances via various oxygen patterns in the aeration phase of the reactor cycle ...
This letter extends the work performed at Argonne National Laboratory on the QUADRISO fuel particles concept for High Temperature Reactors. Different configurations of the QUADRISO fuel particles concept are proposed and examined. The concept of QUADRISO f ...
The manufacture of chemicals in microstructured reactors (MSR) has become recently a new branch of chemical reaction engineering focusing on process intensification and safety. MSR have an equivalent hydraulic diameter up to a few hundreds of micrometers a ...
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 ...
Computerised gamma-ray emission tomography has been applied to single PWR UO2 fuel rods, with pellet averaged burnups of 52, 71, 91 and 126 GWd/t respectively, for the determination of 134Cs, 137Cs and 154Eu internal radial distributions. State-of-the-art ...
