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Title and acronym: ADVANCED NUCLEAR SAFETY EVALUATION OF LIQUID METAL USING SYSTEMS [ANSELMUS]

Call: [HORIZON-EURATOM-2021-NRT-01-02] — [Safety of advanced and innovative nuclear design and fuels]

Grant Agreement Number:101061185

Promoter /Coordinator: STUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE (SCK CEN)

Duration: 48 months, from 1/09/2022 to 31/08/2026

Total grant for the University of Pitești (UPIT): 15000 Euro

Local coordinator for the University of Pitești (UPIT): University Lecturer PhD. Bogdan MARINESCU


Summary:

 

Climate change, due to CO2 emission is a problem that needs to be tackled in various ways including optimising energy efficiency and maximising low-carbon sources. In that context it is unwise to a priori discard an essentially carbon free energy source like nuclear fission. Nuclear energy indeed has objectively proven itself a safe and reliable energy source. Yet, fundamental improvements are possible, particularly regarding intrinsic and passive safety on the one hand and waste generation and fuel efficiency on the other hand. Fast neutron advanced nuclear systems hold the key to reach this objective as they can combine intrinsic safety with fuel and waste minimisation.

 

In the EU, the heavy liquid metal (HLM) cooled nuclear systems ALFRED, the European lead fast reactor (LFR) demonstrator, and MYRRHA, a lead-bismuth eutectic (LBE) cooled accelerator driven system (ADS) that will serve as the only fast spectrum research reactor and irradiation tool in the EU, are clearly among the frontrunners in this field. The priority on HLM systems is reflected in the charter of the European Sustainable Nuclear Industrial Initiative (ESNII), one of the pillars of the Sustainable Nuclear Energy Technology Platform (SNETP). The latter is recognised as a European Technology and Innovation Platform (ETIP) by the European Commission.

 

In support of ALFRED and MYRRHA, ANSELMUS gathers the main actors in the development of HLM systems in the EU, including designers and research and will bundle their expertise in a collaborative spirit to perform the next steps required towards the realisation of innovative HLM technology.

 

Objectives:

 

ANSELSMUS is set up with a single central objective in mind: support deployment of HLM cooled advanced reactors in Europe.

In order to achieve this within the boundaries of the work plan, the central objective is made concrete, measurable and verifiable by defining a set of particular objectives. These were set at the start of the proposal initiative via a consultation round by collecting the input on priorities from the design teams of ALFRED and MYRRHA and feasibility assessments by the research teams. As a result, ANSELMUS will:

  • perform safety evaluation of the designs;
  • assess fuel assembly safety by experiment and modelling;
  • validate the safety performance of essential components;
  • develop non-destructive test-based reactors safety monitoring and vessel inspection for LFR;
  • address the social impact of the HLM systems:
    • by assessing their integration into a low-carbon energy system
    • by addressing social and ethical considerations regarding the safety of advanced nuclear technology.

The objectives make ANSELMUS a pertinent a response to the Horizon-EURATOM-2021-NRT-01-02 call. The particular objectives will be achieved by implementing concrete actions, as planned under each of the following work packages:

  • WP1 - PIRT on HLM systems
  • WP2 - Fuel assembly safety
  • WP3 - Validation of safety systems
  • WP4 - Reactor safety monitoring & inspection
  • WP5 - Social impact of innovative heavy metal cooled nuclear technology
  • WP6 - Dissemination, Education, Training, Communication
  • WP7 - Management

 

Outcomes:

ANSELMUS supports the safety of advanced nuclear reactors that use a heavy liquid metal as a coolant. It focusses on several of the expected outcomes in the call. In particular:

  • safety assessment of advanced and innovative nuclear concepts, their designs and technologies in relation with the requirements of the nuclear safety directive.
  • demonstration of safety performance and reliability of advanced structural materials, and innovative fuels for demonstrators, their monitorability, innovative instrumentation, system integration, component design, balance of plant, for advanced and innovative reactors”
  • development of methods and tools for enhanced modelling assessment, correlations and uncertainties, core and plant advanced surveillance, monitoring, diagnostics and prognostics.

 

Partnership:

 

 tabel

 

Website: http://www.anselmus.eu

 

ANSELMUS work meeting in Romania

 

image001

 

On 20th and 21st of Feb 2023, researchers from SCK CEN, RATEN-ICN and UPIT have met in Romania.

 

Participants have met in the first day at RATEN premises and in the second day in UPIT's Rectorate. The purpose of this 2-day meeting was twofold:

(a) the members of the research teams to better know each other: RATEN-ICN, SCK CEN and UPIT have provided presentations followed by discussions, to gain better insight in working environment and type of work of researchers working in ANSELMUS;

(b) to analyse the sociotechnical integration methodologies and select the most appropriate ones for ANSELMUS Sub-Task 5.2.1. The analysis of the methodologies lasted longer; thus, it has continued during the weeks following the meeting.

 

The last part of the meeting was allocated to sketching a work plan for implementation and discussions over the next subtasks foreseen in Task 5.2 (World Café + survey).

 

Leaflet #1 by UPIT Here 

 

Leaflet #2 by UPIT Here 

 

Newsletter#1 Here

  

 

ANSELMUS World Café workshop in Romania

 

image003

 

 

On 26th of February 2024 UPIT’s social scientists conducted together with researchers from RATEN-ICN a World Café workshop, in the framework of “WP5: Social impact of innovative heavy metal cooled nuclear technology”. The workshop had the title “Social and ethical considerations of advanced nuclear technology” and was attended by 10 researchers from RATEN-ICN.

 

During the workshop, UPIT’s social scientists have moderated workshop’s sessions and used image cards method, have stirred discussions among participants and invited them to reflect on responsibility in research and innovation.  Also, after the workshop they analysed the achievements of the workshop and elaborated the minutes (report) upon this activity. Findings from this workshop will be used to organise future World Cafés meetings with general public, aiming to provide citizens with a balanced basis for discussing lead-cooled fast reactor technology.

 

 

 

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