Gert Van den Eynde

Person

Van den Eynde, Gert

  • Nuclear Systems Physics

Person: Employee

  1. 2020
  2. The nuclear fuel cycle code ANICCA: Verification and a case study for the phase out of Belgian nuclear power with minor actinide transmutation

    Merino Rodríguez, I., Hernandez Solis, A., Messaoudi, N. & Van den Eynde, G., 13 Apr 2020, (Accepted/In press) In : Nuclear Engineering and Design. p. 1-11 11 p.

    Research output: Contribution to journalArticle

  3. A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca

    Hernandez Solis, A., Merino Rodriguez, I., Fiorito, L. & Van den Eynde, G., 29 Mar 2020, PHYSOR 2020: Transition to a Scalable Nuclear Future. Unknown, p. 1-8 8 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  4. Verification of the OpenMC homogenized MYRRHA-1.6 core model

    Hernandez Solis, A., Malambu Mbala, E., Stankovskiy, A. & Van den Eynde, G., 29 Mar 2020, PHYSOR 2020: Transition to a Scalable nuclear future. Unknown, p. 1-1 11 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  5. Reduced order modelling using a POD-based identification method for parametrized PDEs

    Van den Eynde, G., Belloni, F., Star, S., Degroote, J. & Vierendeels, J., 1 Mar 2020, Proceedings of the 6th European Conference on Computational Mechanics: Solids, Structures and Coupled Problems, ECCM 2018 and 7th European Conference on Computational Fluid Dynamics, ECFD 2018. CIMNE - International Centre for Numerical Methods in Engineering, p. 796-805 10 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  6. 2019
  7. Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies

    Villacorta Skarbeli, A., Merino Rodriguez, I., Alvarez Velarde, F., Hernandez Solis, A. & Van den Eynde, G., 30 Oct 2019, In : Annals of nuclear energy. 137, p. 1-9 9 p., 107160.

    Research output: Contribution to journalArticle

  8. POD-identification reduced order model of linear transport equations for control purposes

    Star, S., Belloni, F., Van den Eynde, G. & Degroote, J., 5 Mar 2019, In : International journal for numerical methods in fluids. 90, 8, p. 375-388 8 p.

    Research output: Contribution to journalArticle

  9. 2018
  10. The VENUS-F Reactor for Nuclear Data Validation

    Krása, A., Baeten, P., Fiorito, L., Kochetkov, A., Messaoudi, N., Stankovskiy, A., Van den Eynde, G., Vittiglio, G. & Wagemans, J., 19 Nov 2018, Reactor Dosimetry: 16th International Symposium: ASTM STP 1608. E10.05 ed. ASTM International, p. 286-295 10 p. STP160820170078

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  11. Nuclear data uncertainty analysis for the Po-210 production in MYRRHA

    Fiorito, L., Stankovskiy, A., Hernandez Solis, A., Van den Eynde, G. & Zerovnik, G., 14 Nov 2018, In : EPJ N - Nuclear Sciences and Technologies. 4, p. 1-9 9 p.

    Research output: Contribution to journalArticle

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