The technical topics to be addressed in SESAME were defined following a thorough identification and prioritisation process. This process selected the topics most relevant to the designers and to the safety assessment activities in ESNII. The experience and knowledge gained from previous and continuing EU framework projects, roadmaps, reports and strategic documents from international organisations and open (scientific) literature and conference proceedings were first identified. Feedback was then collected from ESNII representatives and designers in order to prioritise the topics.

Complemented by several meetings, this process set the focus of the work to be carried out in SESAME. Activities cover: the assessment of thermal fluctuations, vibrations, core thermal-hydraulics, pool thermal-hydraulics and integral system thermal-hydraulics, as well as the establishment of best practice guidelines, improved V&V methodologies and uncertainty quantification.

The SESAME project is complementary to the thermal-hydraulic work package in the European MYRTE project. While SESAME focuses on pre-normative, fundamental, safety-related, generic challenges, MYRTE will focus on MYRRHA specific challenges. Both projects will benefit from the developments undertaken in each project and will interact closely as many partners are involved in both.

The scientific and experimental knowledge and findings stemming from SESAME will be shared with the research and scientific community, industry, universities, international and European projects and initiatives, and the general public. Publications are planned and Best Practice Guidelines, improved V&V methodologies for liquid metal flow simulation and a Nuclear Liquid Metal Thermal-hydraulics Textbook will be developed for the industry and research communities interested in liquid metal cooled fast reactors. Training courses and material for CFD code training will be also developed for universities and student networks.

In addition, a Senior Advisory Committee was established to participate in the dissemination and exploitation of the foreground results. This Senior Advisory Committee includes representatives of the fast reactor designs and a representative from the US Nuclear Energy Advanced Modelling and Simulation (NEAMS) program. Its main objectives will be to:

  • provide independent opinion on progress achieved
  • ensure tight interaction between the project and system designers, who are the end-users of the project results (i.e. new models, simulation tools and reference databases)
  • assess the project’s performance, allowing to adjust dynamically the project according to designer requirements, if necessary and possible
  • exchange on international knowledge and practical experience