Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions
Graph Chatbot
Chattez avec Graph Search
Posez n’importe quelle question sur les cours, conférences, exercices, recherches, actualités, etc. de l’EPFL ou essayez les exemples de questions ci-dessous.
AVERTISSEMENT : Le chatbot Graph n'est pas programmé pour fournir des réponses explicites ou catégoriques à vos questions. Il transforme plutôt vos questions en demandes API qui sont distribuées aux différents services informatiques officiellement administrés par l'EPFL. Son but est uniquement de collecter et de recommander des références pertinentes à des contenus que vous pouvez explorer pour vous aider à répondre à vos questions.
An improved version of the FALCON fuel performance code is used to model the thermal-mechanical behaviour of the test rod in the CABRI high-burnup RIA test CIP0-1. First, the original FALCON code (version MOD01) is modified by introducing new routines yiel ...
The FAST code system is a general tool for analyzing advanced reactors from the viewpoint of the static and dynamic behavior of the whole reactor system. It includes an integrated three-dimensional representation of the core neutronics, appropriate modelin ...
Within the European Union, the two major breeding blanket concepts presently being developed are the helium cooled pebble bed (HCPB), and the helium cooled lithium lead (HCLL) blankets. For both concepts, different conceptual designs are being discussed wi ...
The gas lift pump concept based on the bubbling of an inert gas into the primary reactor coolant to enhance natural circulation is currently considered in a number of PbBi-cooled reactor concepts. Thus, the analysis of available void fraction data and the ...
Future nuclear power plants like the very high temperature reactor or the gas cooled fast reactor need materials able to comply with extreme operating conditions (temperature, cooling gas, radiation). Advanced materials like oxide dispersion strengthened ( ...
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 ...
One of the main goals of the FAST project at PSI is to establish a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants. Both static and tran ...
Pressure drop in the ITER PFCI cable-in-conduit conductor (CICC) has been measured at CRPP using pressurized water at room temperature. The PFCI conductor is a dual channel CICC and the coolant flows in parallel in the central channel and in the annular bu ...
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 ...
A detailed three-dimensional, continuous-energy MCNP4B model of the LWR-PROTEUS critical facility has been developed for the analysis of whole-reactor characteristics using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section sets. The model has been applied to t ...