Description of Work

Activity Summaries per Work Packages – Period 1

WP 1 – Coordination and Support for an Integrated Research Programme on Nuclear Materials

The aim of the work package is to support the JPNM in its strategic approach to an Integrated Research Programme (IRP). Therefore networking and integrating activities like a vision paper and periodic road-maps, management of calls and built up contacts with public authorities have to be strengthen. Set up and maintenance of a web portal and a good knowledge dissemination together with a strategic planning for T&E are further important issues.

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WP 2– Modelling of irradiation-induced hardening and creep in F/M alloys 

In WP2, electronic structure, atomistic and dislocation calculation techniques are combined in order to provide an explanation in terms of physical mechanisms for the experimental observations concerning irradiation hardening and creep in high-Cr ferritic/martensitic steels. These are modelled as Fe-Cr-X alloys (where X stands for any additional element) in the case of the study of irradiation hardening, and as Fe in the case of the modelling of irradiation creep.

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WP 3 – Characterization of ceramic composites for GFRs and LFRs 

The general objective of WP3 is the characterization of ceramic composites for GFRs and LFRs. The activities were organised in four different sub tasks, as described in the following table. SiC/SiC composites are considered very promising candidates for GFR fuel cladding. In order to demonstrate this, full ceramic SiC/SiC and hybrid SiC/SiC with a tantalum liner clad sections are being fabricated (3.1) and assessed (3.2 and 3.3). Task 3.4 deals with a different kind of ceramic composites, MAX phase cermets, particularly promising for LFR pump impeller.

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WP 4 – Characterization of ODS alloys for LFR and SFR cladding

The main achievements during this 1st 18 months period are:

  • Distribution of ODS bars and cladding tubes (CEA)
  • Preparation and distribution of GESA-treated ODS plates (KIT)
  • Definition of testing conditions (CEA, CIEMAT, HZDR, KIT, VTT)
  • Microstructural examination of bars and tubes: initial results available (CEA, CIEMAT, EDF, HZDR, ENEA)
  • Microplasticity of ODS alloys studies: preliminary results available (CEA, PSI)
  • Fracture toughness and small punch results of ODS cladding tubes (CEA, CIEMAT)

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MatISSE paper selected as best 2017 paper in the Journal of Nuclear Materials

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