Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics
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.
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 ...
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 ...
Synchrotron radiation induced total reflection X-ray fluorescence (TXRF) and conventional 45 degrees energy dispersive X-ray fluorescence analysis (EDXRF) using a 150-nm-thick AP1 (TM) film as sample carrier have been exploited for the elemental analysis o ...
Pore size distribution, porosities and consequently derived densities are key parameters for the qualification of inert matrix fuel (IMF). Porous features must be determined accurately for assessing the in-pile behaviour of the fuel. The analytical methodo ...
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 ...
An effective way to reduce the large quantities of Pu currently accumulated worldwide would be to use uranium-free fuel in light water reactors (LWRs) so that no new Pu is produced. Such a possibility could be provided by an LWR fuel consisting of Pu in a ...
A SOFC concept based on microtubular cells is presented. Mechanical tests and modelling show viability for fast thermal cycling in air for both zirconia and ceria electrolyte tubes. To combine advantages of both these materials, the concept includes a thin ...
Simulated zirconium oxide-based inert matrix fuel (IMF) has been prepared using cerium oxide replacing plutonium oxide, following the conventional pelletising route, in which an improved two-stage attrition mill was employed. Different methods have been ap ...
The most efficient way to enhance plutonium consumption in light water reactors is to eliminate the production of plutonium all together. This requirement leads to fuel concepts in which the uranium is replaced by an inert matrix. At PSI, studies have focu ...
Light water reactor (LWR) neutronics codes and cross-section libraries need further qualification when used for the calculation of inert matrix fuel (IMF) cells. Three types of validation efforts have been undertaken for the PuO2-Er2O3-ZrO2 IMF concept und ...
