Gert Van den Eynde

Person

Van den Eynde, Gert

  • Nuclear Systems Physics

Person: Employee

  1. Neutron-induced nuclear data for the MYRRHA fast spectrum facility

    Romojaro, P., Zerovnik, G., Alvarez-Velarde, F., Stankovskiy, A., Kodeli, I., Fiorito, L., Diez, C. J., Cabellos, O., Garcia-Herranz, N., Heyse, J., Paradela, C., Schillebeeckx, P. & Van den Eynde, G., 18 Sep 2017, EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. Vol. 146. p. 1-4 4 p. 09007. (EPJ Web of Conferences).

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

  2. Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations

    Romojaro, P., Alvarez-Velarde, F., Kodeli, I., Stankovskiy, A., Diez, C. J., Cabellos, O., Garcia-Herranz, N., Heyse, J., Schillebeeckx, P., Van den Eynde, G. & Zerovnik, G., 28 Nov 2016, In: Annals of nuclear energy. 101, p. 330-338

    Research output: Contribution to journalArticlepeer-review

  3. MYRRHA – Multi-purpose hYbrid Research Reactor for High-tech Applications

    Romojaro, P., Fiorito, L., Stankovskiy, A., Van den Eynde, G., Fernandez, R., Kennedy, G., De Bruyn, D., Engelen, J., Vandeplassche, D. & Aït Abderrahim, H., 11 Nov 2021, In: SNE - Sociedad Nuclear Española - Technical Notes. p. 1-9 9 p., NT-01-21.

    Research output: Contribution to journalArticlepeer-review

  4. Computational Intelligence in Nuclear Applications: Lessons Learned and Recent Developments

    Ruan, D., Hines, W., Pazsit, I. & Van den Eynde, G., 2005, In: Progress in Nuclear Energy. 46, 3-4, p. 165-387

    Research output: Contribution to journalArticlepeer-review

  5. Design of a fuel element for a lead-cooled fast reactor

    Sobolev, V., Malambu Mbala, E., Aït Abderrahim, H. & Van den Eynde, G., 31 Mar 2009, In: Journal of Nuclear Materials. 385, 2, p. 392-399

    Research output: Contribution to journalArticlepeer-review

  6. Development and validation of ALEPH Monte Carlo burn-up code

    Stankovskiy, A., Van den Eynde, G., Vidmar, T. & Malambu Mbala, E., 11 Aug 2011, Nuclear measurements, Evaluations and Applications - NEMEA-6. Paris, France, p. 161-170

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

  7. Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research Reactor

    Stankovskiy, A., Malambu Mbala, E., Van den Eynde, G., Diez, C. & Krása, A., 30 Apr 2014, In: Nuclear Data Sheets. 118, p. 513-515

    Research output: Contribution to journalArticlepeer-review

  8. Sensitivity analysis of the nuclear data for MYRRHA reactor modelling

    Stankovskiy, A., Van den Eynde, G., Cabellos, O., Diez, C., Schillebeeckx, P., Heyse, J. & Krása, A., 29 Aug 2014, Nuclear Measurements, Evaluations and Applications (NEMEA-7) Collaborative International Evaluated Library Organisation (CIELO). Paris, France, Vol. 1. p. 267-275

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

  9. Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems

    Stankovskiy, A., Van den Eynde, G. & Baeten, P., 10 Apr 2012, In: Science and Technology of Nuclear Installations. 2012, 1, p. 1-12

    Research output: Contribution to journalArticlepeer-review

  10. 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 journalArticlepeer-review

ID: 32341