Gert Van den Eynde

Person

Van den Eynde, Gert

  • Nuclear Systems Physics

Person: Employee

  1. 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 journalArticlepeer-review

  2. Determination of the subcriticality level using the 252Cf source-detector method

    Baeten, P., Lafuente, A., Janssens, J., Kochetkov, A., Pazsit, I., Van Grieken, C. & Van den Eynde, G., 3 Mar 2010, In: Annals of nuclear energy. 37, 5, p. 740-752 13 p.

    Research output: Contribution to journalArticlepeer-review

  3. 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 journalArticlepeer-review

  4. 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 paperpeer-review

  5. 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 paperpeer-review

  6. 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 paperpeer-review

  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 journalArticlepeer-review

  8. ADVANTG hybrid code application for the analysis of neutron field depression in uranium foils activated in the MARK III converter of the BR1 reactor

    Çelik, Y., Malambu Mbala, E., Van den Eynde, G., Krása, A. & Wagemans, J., 31 Oct 2019, In: Nuclear Engineering and Design. p. 1-11 11 p., 110384.

    Research output: Contribution to journalArticlepeer-review

  9. Studies of MYRRHA using thorium fuel

    Barlow, R., Burlison, J., Edwards, T., Healy, A., Masterson, A., Aït Abderrahim, H., Malambu Mbala, E. & Van den Eynde, G., 11 May 2016, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES). 17 ed. Vol. 41. p. 7175-7180 6 p. (International Journal of Hydrogen Energy).

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

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