CONFIRM: Uranium free fuels for accelerator driven systems - collaboration on oxide and nitride fuel irradiation and modelling

• Research unit: EU RFP
• Project number: 00.0039

Key words (English)

Nitride fuel fabrication; uranuim free fuel; direct coagulation casting;
Nuclear Fission; Radioactive Waste; Safety;
JRC

Alternative project number (English)

EU project number: FIKW-2000-00096

Research programs (English)

EU-programme: 5. Frame Research Programme - 5.5.2 Nuclear fission

Short description (English)

See abstract

Partners and International Organizations (English)

Coordinator: KTH, Stockholm (S)

Abstract (English)

Accelerator driven systems are candidates for burning of uranium free fuels like nulear 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 irradiation of oxide and nitride uranium free fuels 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.

References in databases (English)

Swiss Database: Euro-DB of the
State Secretariat for Education and Research
Hallwylstrasse 4
CH-3003 Berne, Switzerland
Tel. [phone]
Swiss Project-Number: 00.0039