Conceptual core design study for a high-flux LFR demonstrator

A preconceptual core design study for a pool-type Lead-cooled Fast Reactor (LFR) demonstrator (DEMO) has been developed in the frame of an I-NERI between the Italian National Agency for the New Technologies, Energy and Sustainable Economic Development (ENEA) and Argonne National Laboratory (ANL), based on the European Lead-cooled System (ELSY) reference concept. A demonstration reactor is expected to prove the viability of technology to be implemented in the first-of-a-kind industrial power plant. DEMO specifications as a nuclear power facility demonstrating ELSY main features and performance, besides validating design methodology and tools, have been defined. Suitable design parameters have been set to meet the foremost objective of reaching a high fast neutron flux while respecting all technological constraints. Preliminary thermal-hydraulic analyses have been carried out to verify safety limits were not exceeded.

► Development of a demonstrator proving LFR technology and overall system behavior.
► Definition of DEMO technical specifications as a demonstrative nuclear power facility.
► High neutron flux for efficient irradiation of fuels and materials to high burn-ups.
► Flat power distribution imposed by the choice of an open fuel assembly design.
► Neutronics performance goals suitably achieved, technological constraints respected.