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"Methodology, Analysis and eXperiments for the ""Safety In MYRRHA Assessment"""

Objective

"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 1700°C 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."
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Coordinator

STUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE

Address

Avenue Herrmann Debroux 40
1160 Bruxelles

Belgium

Activity type

Research Organisations

EU Contribution

€ 2 173 500

Administrative Contact

Ludo Veuchelen (Mr.)

Participants (13)

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REGIA AUTONOMA PENTRU ACTIVITATI NUCLEARE DROBETA TR. SEVERIN RA SUCURSALA CERCETARI NUCLEARE PITESTI

Romania

AGENZIA NAZIONALE PER LE NUOVE TECNOLOGIE, L'ENERGIA E LO SVILUPPO ECONOMICO SOSTENIBILE

Italy

EU Contribution

€ 862 705

KARLSRUHER INSTITUT FUER TECHNOLOGIE

Germany

EU Contribution

€ 742 000

ANSALDO NUCLEARE SPA

Italy

EU Contribution

€ 208 447

GESELLSCHAFT FUR ANLAGEN UND REAKTORSICHERHEIT (GRS) gGmbH

Germany

EU Contribution

€ 66 607

NUCLEAR RESEARCH AND CONSULTANCY GROUP

Netherlands

EU Contribution

€ 101 858

CENTRO DI RICERCA, SVILUPPO E STUDI SUPERIORI IN SARDEGNA SOCIETÀ A RESPONSABILITÀ LIMITATA

Italy

EU Contribution

€ 146 678

KUNGLIGA TEKNISKA HOEGSKOLAN

Sweden

EU Contribution

€ 507 395

HELMHOLTZ-ZENTRUM DRESDEN-ROSSENDORF EV

Germany

EU Contribution

€ 56 850

REGIA AUTONOMA TEHNOLOGII PENTRU ENERGIA NUCLEARA - RATEN

Romania

EU Contribution

€ 276 450

CHALMERS TEKNISKA HOEGSKOLA AB

Sweden

EU Contribution

€ 250 510

INSTITUTE OF ATOMIC ENERGY OF NATIONAL NUCLEAR CENTRE OF REPUBLIC OF KAZAKHSTAN

Kazakhstan

EU Contribution

€ 57 000

CENTRO DE INVESTIGACIONES ENERGETICAS, MEDIOAMBIENTALES Y TECNOLOGICAS-CIEMAT

Spain

EU Contribution

€ 50 000

Project information

Grant agreement ID: 323312

Status

Closed project

  • Start date

    1 November 2012

  • End date

    31 October 2018

Funded under:

FP7-EURATOM-FISSION

  • Overall budget:

    € 10 087 542

  • EU contribution

    € 5 500 000

Coordinated by:

STUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE

Belgium