Organization profile

Introduction / mission

The exhaust of a fusion reactor must endure the harshest conditions of any man made object. Our mission is develop liquid metal heat shields that are up to this task.

Highlighted phrase

Improved performance of liquid metal heat shields will not only enable DEMO, but will also allow the design of more practical and more economical future fusion power plants

Organisational profile

The next generation fusion reactor, DEMO, will deliver electricity to the grid. Construction for the European DEMO will be started halfway this century, by the European organization EUROfusion. This reactor will likely require liquid metal heat shields to ensure sufficient lifetime, as well as sufficient robustness to make operation practical. Improved performance of liquid metal heat shields, however, will not only enable DEMO. It will also allow the design of smaller, more economical, and more practical future fusion power plants. Our group collaborates closely with EUROfusion to achieve this task, as well as the Dutch Institute For Fundamental Energy Research (DIFFER), and the international fusion community.

The heat shields in a divertor are exposed to intense plasma fluxes (~10 MW/m2, comparable to spacecraft re-entry), and to millisecond transients during plasma disruptions (~80 GW/m2). On top of that the divertor lives a nuclear environment, under constant neutron bombardment. Liquid metal heat shields are particularly suited for this challenge. Our group investigates multiple facets of this technology. Firstly, we experimentally and numerically investigate the power handling capacity. Which involves evaporative and radiative processes of the liquid metal in the plasma. This is done in particular on the Magnum-PSI device located at DIFFER, which replicates the conditions on the reactor wall. Secondly, we develop new designs, and investigate their performance. For example, we developed a 3D-printed tungsten substrate to hold the liquid metal, which allowed for optimizing its performance. The primary focus of the group, for the near future, is the development and testing of realistic shield concept for the European DEMO reactor. 

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    Research Output

    • 9 Article
    • 1 Conference contribution
    • 1 Paper
    • 1 Phd Thesis 1 (Research TU/e / Graduation TU/e)

    Deuterium retention in Sn-filled samples exposed to fusion-relevant flux plasmas

    Ou, W., Al, R. S., Vernimmen, J. W. M., Brons, S., Rindt, P. & Morgan, T. W., Feb 2020, In : Nuclear Fusion. 60, 2, 16 p., 026008.

    Research output: Contribution to journalArticleAcademicpeer-review

  • Experimental evidence of enhanced recombination of a hydrogen plasma induced by nitrogen seeding in linear device Magnum-PSI

    Magnum-PSI Team, Perillo, R., Akkermans, G. R. A., Classen, I. G. J., Vijvers, W. A. J., Chandra, R., Jesko, K., Korving, S., Vernimmen, J. W. M. & de Baar, M. R., 1 May 2019, In : Nuclear Materials and Energy. 19, p. 87-93 7 p.

    Research output: Contribution to journalArticleAcademicpeer-review

    Open Access
    File
  • 4 Citations (Scopus)
    42 Downloads (Pure)

    Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI

    Rindt, P., Morgan, T. W., van Eden, G., Jaworski, M. A. & Cardozo, N. J. L., 15 Mar 2019, In : Nuclear Fusion. 59, 5, 13 p., 056003.

    Research output: Contribution to journalArticleAcademicpeer-review

    Open Access
    File
    2 Citations (Scopus)
    3 Downloads (Pure)

    Student theses

    Are droplet-impact and laser-ablation splashing commutable?

    Author: Hermens, J. C., May 2020

    Supervisor: Rindt, P. (Supervisor 1), Versolato, O. O. (External person) (External coach), Beckers, J. (Supervisor 2) & Lopes Cardozo, N. J. (Supervisor 2)

    Student thesis: Master

    File

    Design of a 3D printed pre-loaded liquid lithium divertor target and testing at Magnum-PSI

    Author: Mata Gonzalez, J., 2017

    Supervisor: Rindt, P. (Supervisor 1) & Lopes Cardozo, N. J. (Supervisor 2)

    Student thesis: Master

    File