Publications associées à Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

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.

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Andreas Pautz, Winfried Zwermann, Alexander Aures

The impact of nuclear data uncertainties is studied for the reactor power and the reactivity during control rod withdrawal transients with reactivity insertions of 0.5

and 0.97

, respectively, for a PWR mini-core model. Multi-group cross sections, the mul ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

Graph Chatbot

Chattez avec Graph Search

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Experimental and numerical study of stochastic branching noise in nuclear reactors

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Review of kinetic modulation experiments in low power nuclear reactors

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Nanoscale mechanism of UO2 formation through uranium reduction by magnetite

Experimental and numerical study of stochastic branching noise in nuclear reactors

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Review of kinetic modulation experiments in low power nuclear reactors

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Nanoscale mechanism of UO2 formation through uranium reduction by magnetite