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.
Funding SchemeCSC - Cost-sharing contracts
OX11 0QJ Didcot,harwell,chilton
CA20 1PG Seascale
13108 St.paul Les Durance
WA3 6AT Warrington