ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark

Kvizda, Boris; Mayer, Gusztáv; Vácha, Petr; Malesa, Janusz; Siwiec, Arkadiusz; Vasile, A.; Bebjak, S.; Hatala, Branislav

doi:10.1016/j.nucengdes.2019.02.006

Cited by 16 publications

(2 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Over the last couple of decades Europe concentrated on four industrial GenIV fast reactor prototype/demonstrator projects, namely: ASTRID [248], ALFRED [249,250], AL-LEGRO [251] and MYRRHA [29,252], all of them promoted by the European Sustainable Nuclear Industrial Initiative (ESNII-see Annex 2). The first three are, respectively, the sodium, lead and gas cooled GenIV fast reactor demonstrators.…”

Section: Annex 1-geniv Prototypes and Demonstrators In Europementioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

View full text Add to dashboard Cite

Nuclear energy is presently the single major low-carbon electricity source in Europe and is overall expected to maintain (perhaps eventually even increase) its current installed power from now to 2045. Long-term operation (LTO) is a reality in essentially all nuclear European countries, even when planning to phase out. New builds are planned. Moreover, several European countries, including non-nuclear or phasing out ones, have interests in next generation nuclear systems. In this framework, materials and material science play a crucial role towards safer, more efficient, more economical and overall more sustainable nuclear energy. This paper proposes a research agenda that combines modern digital technologies with materials science practices to pursue a change of paradigm that promotes innovation, equally serving the different nuclear energy interests and positions throughout Europe. This paper chooses to overview structural and fuel materials used in current generation reactors, as well as their wider spectrum for next generation reactors, summarising the relevant issues. Next, it describes the materials science approaches that are common to any nuclear materials (including classes that are not addressed here, such as concrete, polymers and functional materials), identifying for each of them a research agenda goal. It is concluded that among these goals are the development of structured materials qualification test-beds and materials acceleration platforms (MAPs) for materials that operate under harsh conditions. Another goal is the development of multi-parameter-based approaches for materials health monitoring based on different non-destructive examination and testing (NDE&T) techniques. Hybrid models that suitably combine physics-based and data-driven approaches for materials behaviour prediction can valuably support these developments, together with the creation and population of a centralised, “smart” database for nuclear materials.

show abstract

Section: Annex 1-geniv Prototypes and Demonstrators In Europementioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

View full text Add to dashboard Cite

show abstract

“…An extensive experimental campaign was carried out to obtain data on the compatibility of base materials (austenitic alloys 316L and 15-15Ti), their welds, AFA, and coated specimens (alumina forming diffusion coatings, ceramic coatings by pulsed laser deposition and by detonation gun spray) with heavy liquid metals (HLM) and He gas. The goal was to clarify the degradation mechanisms and to establish correlations for the design of MYRRHA [10], ALFRED [11] and ALLEGRO [12]. For the first time, a large amount of data has been collected on the compatibility of steels and their welds in contact with these fluids.…”

Section: Testing Under Representative Conditions In Contact With Heav...mentioning

confidence: 99%

Towards a single European strategic research and innovation agenda on materials for all reactor generations through dedicated projects

Malerba

Agostini

Angiolini

et al. 2022

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

The goal of the ORIENT-NM action is to produce a single European strategic vision on research and innovation concerning nuclear materials in the EU, serving all reactor generations and nuclear systems. The key in this endeavour is to focus on advanced materials science practices that, combined with digital techniques, will enable acceleration in materials development, manufacturing, supply, qualification, and monitoring, in support of nuclear energy safety, efficiency, economy and sustainability. The research agenda will be rooted in existing virtuous examples of nuclear materials science projects. Here the results of three of them are summarised, thereby covering different reactor applications and families of materials, as well as a range of advanced material research approaches. GEMMA addressed a number of key areas concerning the development and qualification of metallic structural materials for GenIV reactor conditions, focusing on austenitic steels and their compatibility with several non-aqueous coolants, their welds and the modelling of their stability under irradiation. INSPYRE was an integrated project applying a basic science approach to (U,Pu)O2 fuels, to develop physics-based models for the behaviour of nuclear fuels under irradiation and improve fuel performance codes. Modelling was also the focus of the M4F project, which brought together the fission and fusion materials communities to study the effects of localised deformation under irradiation in ferritic/martensitic steels and to develop good practices to use ion irradiation as a tool to evaluate radiation effects on materials.

show abstract

Modelling of Steel-Concrete-Steel Structure Using FEM Plane Elements

Kubát,

Bílý

2023

Lecture Notes in Civil Engineering

View full text Add to dashboard Cite

ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark

Cited by 16 publications

References 11 publications

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Towards a single European strategic research and innovation agenda on materials for all reactor generations through dedicated projects

Modelling of Steel-Concrete-Steel Structure Using FEM Plane Elements

Contact Info

Product

Resources

About