Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
Related publications (61)
Graph Chatbot
Chat with Graph Search
Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.
DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.
For many years various countries with access to commercial reprocessing services have been routinely recycling plutonium as UO2/PuO 2 mixed oxide (MOX) fuel in light water reactors (LWRs). This LWR MOX recycle strategy is still widely regarded as an interi ...
Zirconium nitride has been proposed as inert matrix material to burn plutonium or to transmute long-lived actinides in accelerator-driven sub-critical systems or fast reactors. In combination with the possibility to fabricate specially shaped fuel pellets, ...
This paper considers the minimization of batch time for an industrial inverse-emulsion polymerization reactor in the presence of uncertainty. A first optimization study resulted in the current industrial practice of a semi-adiabatic profile (isothermal ope ...
The shift toward low-enrichment uranium (LEU) fuel for gas-cooled high-temperature reactors (HTRs) has revealed a lack of experimental data for validating neutronics codes that are used for the design and licensing of such systems. In the framework of the ...
The need for accurate calculational tools for the determination of gamma heating in fast reactors has increased considerably in recent years following the planned modification of certain existing fast breeders into plutonium-burning configurations. The lat ...
New critical experiments in the framework of an IAEA Coordinated Research Program on `Validation of Safety Related Reactor Physics Calculations for Low-Enriched HTR's' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the ...
Predictions from a gyrokinetic toroidal plasma model reproduce for the first time the evolution of Alfven eigenmode (AE) dampings over a range of discharges. The coupling between shear-and kinetic-Alfven waves is responsible for the main source of damping ...
A new calculational scheme has been developed for the accurate assessment of gamma heating in fast reactors, its special feature being the determination of the gamma source distribution that is formulated in a near-to-exact manner. The improved methodology ...
Accidental water ingress in pebble-bed type, high temperature reactor (HTR) cores can result in large positive reactivity changes and in consequent reductions in shutdown margins, since such systems generally tend to be undermoderated. The prediction of su ...
The Pulsed-Neutron-Source technique, commonly used for the measurement of the subcriticality of multiplying systems, suffers from the fact that the values of reactivity obtained are dependent upon calculated correction factors and/or kinetic parameters. Ca ...