Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
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.
Nuclear materials have been successfully employed in commercial fission reactors for many decades. Research and material development for advanced fission system and future thermo-nuclear fusion reactors have acquired maturity while great challenges remain ...
The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...
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, ...
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 ...
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 ...
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 ...
The minimum overall size of a reflected pebble-bed reactor is, in general, considerably smaller than that of the corresponding bare-critical assembly. It becomes meaningful, therefore, to refer to reflector savings in terms of overall size and not just in ...
Thermal creep tests have been conducted on the EUROFER 97 reduced activation ferritic/martensitic (RAFM) steel and two kinds of oxide dispersion strengthened (ODS) EUROFER 97 steels, which were manufactured using slightly different powder metallurgy techni ...
Reduced activation ferritic/martensitic (RAFM) steels are the reference structural materials for future fusion reactors. They have proven to be a good alternative to austenitic steels for their higher swelling resistance, lower damage accumulation and impr ...
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 ( ...