Gert Van den Eynde

Person

Van den Eynde, Gert

  • Nuclear Systems Physics

Person: Employee

  1. 2021
  2. Accelerator Driven Subcritical Systems

    Aït Abderrahim, H., De Bruyn, D., Van den Eynde, G. & Fernandez, R., 1 Jul 2021, Encyclopedia of Nuclear Energy: Reference Module in Earth Systems and Environmental Sciences. 1 ed. Elsevier, p. 1-21 21 p.

    Research output: Contribution to report/book/conference proceedingsChapter

  3. 2020
  4. Depletion uncertainty analysis to the MYRRHA fuel assembly model

    Hernandez Solis, A., Stankovskiy, A., Fiorito, L. & Van den Eynde, G., 30 Sep 2020, In : EPJ Web of Conferences. 239, p. 1-4 4 p., 12001.

    Research output: Contribution to journalArticle

  5. Partitioning & transmutation contribution of MYRRHA to an EU strategy for HLW related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS

    Aït Abderrahim, H., Baeten, P., Sneyers, A., Schyns, M., Schuurmans, P., Kochetkov, A., Van den Eynde, G. & Biarrotte, J-L., 30 Jun 2020, FISA 2019: 9th European commission conference on EURATOM research and training in safety of reactor systems. 2020 ed. Luxembourg: Publications Office of the European Union, Vol. KI-01-19-009-EN-N. p. 346-358 13 p.

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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 2019
  11. 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

  12. 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

  13. MYRRHA accelerator driven sytem programme: Recent progress and perspectives

    Aït Abderrahim, H., De Bruyn, D., Dierckx, M., Fernandez, R., Popescu, L., Schyns, M., Stankovskiy, A., Van den Eynde, G. & Vandeplassche, D., 2019, Nuclear Power Engineering. p. 1-13 13 p. UDC 621.039.5. (Nuclear Power Engineering Ru; vol. 2).

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

  14. 2018
  15. 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

  16. 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

  17. Sensitivity and uncertainty analysis of betaeff for MYRRHA using a Monte Carlo technique

    Iwamoto, H., Stankovskiy, A., Van den Eynde, G. & Fiorito, L., 14 Nov 2018, In : EPJ N - Nuclear Sciences and Technologies. 4, 42, 7 p.

    Research output: Contribution to journalArticle

  18. High-energy nuclear data uncertainties propagated to MYRRHA safety parameters

    Stankovskiy, A., Iwamoto, H., Çelik, Y. & Van den Eynde, G., 11 Jun 2018, In : Annals of nuclear energy. 120, p. 207-218 15 p.

    Research output: Contribution to journalArticle

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