Methodology, Analysis and eXperiments for the "Safety In MYRRHA Assessment" (MAXSIMA)
Research Project, 2012 – 2018

The Strategic Research Agenda of the EU Sustainable Nuclear Energy Technical platform requires new large infrastructures for its successful deployment. MYRRHA has been identified as a long term supporting research facility for all ESNII systems and as such put in the high-priority list of ESFRI. The goal of MAXSIMA is to contribute to the safety in MYRRHA assessment.MAXSIMA has five technical work-packages. The first contains safety analyses to support licensing of MYRRHA. Design-based, design extended and severe accident events will be studied with a focus on transients potentially leading to fuel pin failures. Fuel assembly blockage and control system failure are the least unlikely events leading to core damage. For code validation a thermal-hydraulic study of different blockage scenarios of the fuel bundle and tests of the hydrodynamic behaviour of a new buoyancy driven control/safety system are planned. Both are supported by numerical simulations. Safety of the Steam Generator is treated by looking at consequences and damage propagation of a SG Tube Rupture event (SGTR) and by characterising leak rates and bubble sizes from typical cracks in a SGTR. Additionally a leak detection system and the drag on bubbles travelling through liquid LBE are studied. MOX fuel segment qualification with transient irradiations is a big step in licensing. MAXIMA include validation experiments for safety computer codes involving core damage scenarios with high temperature MOX-LBE interactions. Fuel-coolant-clad chemistry is studied up to 1700C and a core melt experiment in a reactor is prepared to assess the interaction of LBE with molten fuel. Following the Fukushima accident, effort is put on development of enhanced passive safety systems for decay heat removal and on confinement analyses for HLM systems. A separate work package is dedicated to education and training. Beside workshops, lecture series and training sessions, virtual-safety simulator software will be developed.


Teodora Retegan Vollmer (contact)

Chalmers, Chemistry and Chemical Engineering, Energy and Material


Ansaldo Nucleare

Genova, Italy

Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (Ciemat)

Madrid, Spain

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS)

Köln, Germany


Berlin, Germany

Institute Of Atomic Energy Of National Nuclear Centre Of Republic Of Kazakhstan

Kurchatov, Kazakstan

Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)

Roma, Italy

Karlsruhe Institute of Technology (KIT)

Karlsruhe, Germany

Regia Autonoma Tehnologii Pentru Energia Nucleara - Raten

Mioveni, Romania

Royal Institute of Technology (KTH)

Stockholm, Sweden

Sardegna Ricerce (CRS4)

Cagliari, Italy

Studiecentrum voor Kernenergie (SCK-CEN)

Brussel, Belgium


European Commission (EC)

Project ID: EC/FP7/323312
Funding Chalmers participation during 2012–2018

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