Objective
Accelerator driven systems are candidates for burning of uranium free fuels like nuclear waste. As the fraction of waste lost to the secondary waste stream in a multi recycling strategy decreases with increased fuel burnup, an important objective of uranium free fuel development for ADS is to achieve high burnup without loss of safety margins. From the fuel perspective, burnup is limited by swelling rates and pin pressurization. These issues can be addressed by use of optimised fuel pellet, pin and assely designs. This proposal suggests a program for modelling, development and irradiaton of oxide and nitride uranium free fuel s under normal operating conditions as well as under power transients. The objective is to identify a reference oxide fuel for an ADS demo facility, and to investigate safety properties of nitride alternatives.
Fields of science
CORDIS classifies projects with EuroSciVoc, a multilingual taxonomy of fields of science, through a semi-automatic process based on NLP techniques.
CORDIS classifies projects with EuroSciVoc, a multilingual taxonomy of fields of science, through a semi-automatic process based on NLP techniques.
Programme(s)
Topic(s)
Call for proposal
Data not availableFunding Scheme
CSC - Cost-sharing contractsCoordinator
10044 STOCKHOLM
Sweden