Gert Van den Eynde

Person

Van den Eynde, Gert

  • Nuclear Systems Physics

Person: Employee

  1. XT-ADS: Neutronics, Shielding and Radiation Damage Calculations

    Romanets, Y., Aït Abderrahim, H., De Bruyn, D., Dagan, R., Gonçalves, I., Maschek, W., Rimpault, G., Struwe, D., Van den Eynde, G., Vaz, P. & Vicente, C., Nov 2009, In: Nuclear Technology. 168, 2, p. 537-541

    Research output: Contribution to journalArticlepeer-review

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. Impact of intermediate and high energy nuclear data on the neutronic safety parameters of MYRRHA accelerator driven system

    Stankovskiy, A., Çelik, Y. & Van den Eynde, G., 18 Sep 2017, EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. 2017 ed. Vol. 146. p. 1-6 6 p. 09001. (EPJ Web of Conferences).

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

  13. 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 journalArticlepeer-review

  14. Impact of nuclear data uncertainties on neutronics parameters of MYRRHA/XT-ADS

    Sugawara, T., Stankovskiy, A., Sarotto, M., Van den Eynde, G. & Malambu Mbala, E., 11 Aug 2011, Nuclear Measurements, Evaluations and Applications - NEMEA-6. Paris, France, Vol. 1. p. 27-36

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

  15. Nuclear data sensitivity/uncertainty analysis for XT-ADS

    Sugawara, T., Sarotto, M., Stankovskiy, A., Van den Eynde, G. & Malambu Mbala, E., 5 May 2011, In: Annals of nuclear energy. 38, 5, p. 1098-1108

    Research output: Contribution to journalArticlepeer-review

  16. Analysis of the Parameters of the Target Unit of a Molten-Salt Subcritical Electronuclear Facility

    Titarenko, Y. E., Batyaev, V. F., Pavlov, K. V., Titarenko, A. Y., Rogov, V. I., Zhivun, V. M., Kulevoy, T. V., Sobolevsky, N. M., Voloschenko, A. M., Didenko, A. N., Polozov, S. M., Koldobsky, A. B., Alekseev, P. N., Fomichenko, P. A., Dudnikov, A. N., Nevinitsa, V. A., Sedov, A. A., Frolov, A. A., Lubina, A. S., Balanin, A. L., Subbotin, S. A., Subbotin, A. S., Stankovskiy, A., Van den Eynde, G. & Mashnik, S., 1 Nov 2014, In: Atomic Energy. 117, 1, p. 19-28 9 p., 117.

    Research output: Contribution to journalArticlepeer-review

  17. Experimental Results from the VENUS-F Critical Reference State for the GUINEVERE Accelerator Driven System Project

    Uyttenhove, W., Baeten, P., Ban, G., Billebaud, A., Chabod, S., Dessagne, P., Kerveno, M., Kochetkov, A., Lecolley, F-R., Lecouey, J-L., Marie, N., Mellier, F., Steckmeyer, J-C., Thyébault, H-E., Vittiglio, G., Wagemans, J. & Van den Eynde, G., Dec 2012, In: IEEE transactions on nuclear Science. 59, 6, p. 3194-3200

    Research output: Contribution to journalArticlepeer-review

  18. The neutronic design of a critical lead reflected zero-power reference core for on-line subcriticality measurements in Accelerator Driven Systems

    Uyttenhove, W., Baeten, P., Van den Eynde, G., Kochetkov, A., Lathouwers, D., Carta, M. & Wagemans, J., Apr 2011, In: Annals of nuclear energy. 38, 7, p. 1519-1526

    Research output: Contribution to journalArticlepeer-review

  19. Status of the EC-FP7 Project ARCAS: Comparing the economics of accelerator-driven systems and fast reactors as minor actinide burners

    Van den Eynde, G., Romanello, V., Martin-Fuertes, F., Zimmerman, C., Lewin, B. G., van Heek, A. & Baeten, P., May 2013, Actinide and Fission Product Partitioning and Transmutation - Twelfth Information Exchange Meeting. Paris, France, p. 301-313

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

  20. Calculating near-singular eigenvalues of the neutron transport operator with arbitrary order anisotropic scattering

    Van den Eynde, G., Beauwens, R., Mund, E., Aït Abderrahim, H. & De Bruyn, D., 1 Jul 2010, In: Mathematics and Computers in Simulation. 80, 11, p. 2216-2230

    Research output: Contribution to journalArticlepeer-review

  21. The reactor point-kinetics equations: semi-analytical methods versus numerical methods

    Van den Eynde, G. & Baeten, P., 11 Jul 2005, The reactor point-kinetics equations: semi-analytical methods versus numerical methods. Paris

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

  22. ALEPH2 Monte Carlo burn up code

    Van den Eynde, G., Stankovskiy, A., Malambu Mbala, E., Vidmar, T. & Baeten, P., 19 Sep 2011, Proceedings of the International Conference on Nuclear Criticality Safety. Paris, France

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

  23. Neutronic design of the XT-ADS core with In-Pile-Sections

    Van den Eynde, G., Sobolev, V., Malambu Mbala, E., Maes, D., Lamberts, D., Aït Abderrahim, H., Mansani, L., Giraud, B., Hogenbirk, A., Vaz, P., Romanets, Y., Vincente, M-C., Coddington, P., Mikityuk, K., Struwe, D., Schikorr, M., Rimpault, G. & Artioli, C., 1 Apr 2008, Utilisation and Reliability of High Power Proton Accelerators (HPPA5). Paris, France, Vol. 1. p. 357-365

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

  24. Progress of the MYRRHA ADS Project in Belgium

    Van den Eynde, G., Aït Abderrahim, H., De Bruyn, D. & Baeten, P., May 2013, Actinide and Fission Product Partitioning and Transmutation - Twelfth Information Exchange Meeting (IEMPT12). Paris, France, p. 158-168

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

  25. An updated core design for MYRRHA

    Van den Eynde, G., Malambu Mbala, E., Stankovskiy, A., Fernandez, R. & Baeten, P., 28 Sep 2014, Proceedings of PHYSOR 2014. Japan

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

  26. The Boundary Sources Method with Anisotropic Scattering

    Van den Eynde, G., Beauwens, R., Mund, E. & Aït Abderrahim, H., 12 Sep 2005, The Boundary Sources Method with Anistropic Scattering. Avignon

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

  27. Neutron transport with anisotropic scattering

    Van den Eynde, G. & Aït Abderrahim, H., 12 May 2005, Université Libre de Bruxelles: ULB - Université Libre de Bruxelles. 190 p.

    Research output: ThesisDoctoral thesis

  28. Comments on "General Eigenvalue Spectrum in a One-Dimensional Slab Geometry Transport Equation"

    Van den Eynde, G. & Aït Abderrahim, H., 1 May 2006, In: Nuclear Science and Engineering. 153, 1, p. 98-100

    Research output: Contribution to journalArticlepeer-review

  29. Comments on "A Resolution of the Stiffness Problem of Reactor Kinetics"

    Van den Eynde, G. & Aït Abderrahim, H., 1 Jun 2006, In: Nuclear Science and Engineering. 153, 2, p. 200-202

    Research output: Contribution to journalArticlepeer-review

  30. The Boundary Source Method with Arbitrary Order Anisotropic Scattering

    Van den Eynde, G., Beauwens, R., Mund, E. & Aït Abderrahim, H., 1 Feb 2007, In: Nuclear Science and Engineering. 155, 2, p. 300-309

    Research output: Contribution to journalArticlepeer-review

  31. Calculating the discrete spectrum of the transport operator with arbitrary order anisotropic scattering

    Van den Eynde, G., Beauwens, R., Mund, E. & Aït Abderrahim, H., Sep 2007, In: Transport Theory and Statistical Physics. 36, 1-3, p. 179-197

    Research output: Contribution to journalArticlepeer-review

  32. An updated core design for the multi-purpose irradiation facility MYRRHA

    Van den Eynde, G., Malambu Mbala, E., Stankovskiy, A., Fernandez, R. & Baeten, P., 7 Apr 2015, In: Journal of Nuclear Science and Technology. p. 1-1

    Research output: Contribution to journalArticlepeer-review

  33. Development of a Gauss-Chandrasekhar Quadrature for the Boundary Sources Method with Anisotropic Scattering

    Van den Eynde, G., Beauwens, R., Mund, E. & Aït Abderrahim, H., Mar 2008, In: Transport Theory and Statistical Physics. 37, 2-4, p. 344-360

    Research output: Contribution to journalArticlepeer-review

  34. HEXNODYN - A time-dependent three-dimensional hexagonal-Z transport code

    Van den Eynde, G., 2001, Mol, Belgium: SCK CEN. 122 p. (SCK•CEN Reports; no. BLG-894)

    Research output: Report/bookBLG - Open report

  35. Topical Day | From nuclear data to a reliable estimate of spent fuel decay heat

    Van den Eynde, G., Gysemans, M. & Schröder, J., 26 Oct 2017, SCK CEN. 20 p. (SCK•CEN Reports; no. BA-96)

    Research output: Report/bookBook of abstractspeer-review

  36. 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

  37. An easy to implement global variance reduction procedure for MCNP

    van Wijk, A., Van den Eynde, G., Hoogenboom, E. & Baeten, P., Nov 2011, In: Annals of nuclear energy. 38, 11, p. 2496-2503

    Research output: Contribution to journalArticlepeer-review

  38. Secondary SCRAM System for Liquid Metal Cooled Nuclear Reactors: Simulation using Particle-Based Methods and Experimental Validation

    Vanmaercke, S., Van den Eynde, G. & Aït Abderrahim, H., Jan 2012, Louvain la Neuve, Belgium: UCL - Université Catholique de Louvain. 211 p.

    Research output: ThesisDoctoral thesis

  39. Conceptual study of a Complementary Scram System For Liquid Metal Cooled Nuclear Reactors

    Vanmaercke, S., Van den Eynde, G., Tijskens, E. & Bartosiewicz, Y., 27 Sep 2009, 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proceedings. Japan

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

  40. Modelling the Interaction of a Molten Seal and Solid Particles using SPH and DEM Simulations : Application for a Passive New SCRAM System for LMR

    Vanmaercke, S., Van den Eynde, G., Tijskens, E., Bartosiewicz, Y. & Van Tichelen, K., Sep 2011, Nureth-14 Proceedings. Toronto, Canada

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

  41. Preliminary Experimental and Numerical Assessment of a Secondary Scram System for Liquid Metal Cooled Reactors.

    Vanmaercke, S., Van den Eynde, G., Tijskens, E. & Bartosiewicz, Y., 26 Oct 2010, Nuthos 08. China

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

  42. Design of a complementary scram system for liquid metal cooled nuclear reactors

    Vanmaercke, S., Van den Eynde, G., Tijskens, E., Bartosiewicz, Y. & Aït Abderrahim, H., Feb 2012, In: Nuclear Engineering and Design. 243, p. 87-94

    Research output: Contribution to journalArticlepeer-review

  43. Development of a Secondary SCRAM System for Fast Reactors and ADS Systems

    Vanmaercke, S., Van den Eynde, G., Tijskens, E., Bartosiewicz, Y., Scheveneels, G. & Aït Abderrahim, H., Feb 2012, In: Science and Technology of Nuclear Installations. 2012, p. 1-9

    Research output: Contribution to journalArticlepeer-review

  44. Numerical and experimental study of a spherical particle flow in a cylindrical tube under vacuum conditions

    Vanmaercke, S., Tijskens, E., Van den Eynde, G. & Bartosiewicz, Y., Sep 2011, In: Granular Matter. 13, 6, p. 713-721

    Research output: Contribution to journalArticlepeer-review

  45. Study of reactivity effects of fission products and actinides after power transients in PWR NPP

    Vase, G. & Van den Eynde, G., 30 Aug 2012, Mol, Belgium: BNEN - Belgian Nuclear Higher Education Network. 83 p.

    Research output: ThesisMaster's thesis

  46. 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

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