NuFuel & MMSNF 2015

First Workshop on Research into Nuclear Fuel in Europe
and Materials Modeling and Simulation for Nuclear Fuels Workshop
Karlsruhe, Germany, November 16th to 18th, 2015

Updated: Tue 08 Dec 2015, 14:27

Talk 2.5: New Catalog on (U,Pu)O2 Properties For Fast Reactors: Work Plan Of The ESNII+ Project and Perspectives

N. Chauvin1, JP. Ottaviani1, D. Staicu2, S. Van Til3, A. Fedorov3, M. Verwerft4, L. Belovsky5, Z. Hozer6, R. Calabrese7, G. Trillon8, S. Portier9
  • 1: CEA, DEN, DEC
  • 2: European Commission, Joint Research Centre, Institute for Transuranium Elements (ITU), Hermann-von-Helmholtz Platz 1, PO Box 2340, DE–76125 Karlsruhe, Germany
  • 3: NRG, Netherlands
  • 4: SCK
  • 5: UJV
  • 6: MTA
  • 7: ENEA

Abstract

In order to develop the fast neutron systems, three prototypes of the Sodium Fast Reactor, the Gas-cooled Fast Reactor and a heavy liquid metal cooled Accelerator Driven System are studied in Europe: ASTRID (SFR prototype), ALLEGRO (GFR prototype) and MYRRHA (an LBE-cooled ADS system related to the ALFRED LFR-demonstrator). The ESNII+ project with its work package 7-FUEL SAFETY aims to provide a set of oxide fuel properties needed for the fuel element design of each prototype. The improvement of fuel properties will also reduce uncertainties in safety behaviour evaluations, in nominal conditions as well as during transients and will be achieved by the update of the European catalogue on the MOX fuel properties, used for the fuel design of the ESNII prototypes. While the properties of fresh fuel will be updated with new measurements, properties on irradiated mixed oxide fuel will be integrated and a tentative correlation with burn-up will be proposed.

The associated uncertainties have to be rigorously determined; the two main driver criteria for fuel element evaluation are the margin to melt for the fuel and the risk of clad failure. It is commonly assumed that the properties of the fuel yield the dominant contribution to the uncertainties in thermal and mechanical evaluation. The measurements of the main thermal and mechanical properties on fresh and irradiated fuel should enhance the reliability of fuel behaviour calculations and contribute to the design of safer fuel elements for ALLEGRO, ASTRID and MYRRHA. Indeed this work starts with property measurements on existing fresh and irradiated fuel samples, identified to cover the fuel characteristics for ESNII prototypes. The choice of the different samples was the result of an analysis during the project preparation and lead to identify fresh and irradiated existing samples with suitable characteristics.

Finally, this work will be a guidance to focus experimental works on features of interest. Indeed this work plan will start with property measurements on existing fresh and irradiated fuel samples, identified to cover the fuel characteristics for the 3 prototypes.