Graham Kennedy

Person

Kennedy, Graham

  • Nuclear Technology Engineering

Person: Employee

  1. 2022
  2. Predicting fretting wear due to turbulence-induced vibration in a wire-wrapped fuel assembly

    Dolfen, H., De Ridder, J., Brockmeyer, L. A., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-16 16 p. 35577

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

  3. 2021
  4. A multi-stage approach of simulating turbulence-induced vibrations in a wire-wrapped tube bundle for fretting wear prediction

    Dolfen, H., De Ridder, J., Brockmeyer, L., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J., 28 Dec 2021, In: Journal of Fluids and Structures. 109, p. 1-27 27 p., 103460.

    Research output: Contribution to journalArticlepeer-review

  5. 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

  6. 2020
  7. Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly

    Kennedy, G., Van Tichelen, K., Pacio, J., Di Piazza, I. & Uitslag-Doolaard, H., Feb 2020, In: Nuclear Technology. 206, 2, p. 179-190 12 p.

    Research output: Contribution to journalArticlepeer-review

  8. 2019
  9. Thermal Hydraulic Aspects of Liquid Metal Cooled Reactors

    Roelofs, F. (ed.), Van Tichelen, K., Kennedy, G., Rozzia, D., Castelliti, D., Keijers, S. & Fernandez, R., 4 Sep 2019, Duxford, UK: Woodhead publishing (imprint of Elsevier). 462 p. (Energy)

    Research output: Report/bookBook as authorpeer-review

  10. Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

    Roelofs, F., Uitslag-Doolaard, H., Dovizio, D., Blaz, M., Shams, A., Bertocchi, F., Rohde, M., Pacio, J., Di Piazza, I., Kennedy, G., Van Tichelen, K., Obabko, A. & Merzari, E., 24 Aug 2019, In: Nuclear Engineering and Design. 353, 8 p., 110273.

    Research output: Contribution to journalArticlepeer-review

  11. CFD and Experiments for Wire-wrapped Fuel Assemblies

    Roelofs, F., Uitslag-Doolaard, H., Mikuz, B., Dovizio, D., De Santis, D., Shams, A., Bertocchi, F., Rohde, M., Van Tichelen, K., Keijers, S., Kennedy, G., Batta, A., Julio, P., Planquart, P., Obabko, A., Brockmeyer, L., Merzari, E., Vaghetto, R., Hassan, Y., Leonard, D., Martin, M., Steer, M., Delchini, M. & Pointer, W. D., 18 Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 1-14 14 p.

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

  12. Numerical simulations of the turbelence-induced vibrations of a wire-wrapped hexagonal fuel assembly

    Dolfen, H., De Ridder, J., Brockmeyer, L., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J., 18 Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). ANS - American Nuclear Society, p. 5092-5102 11 p.

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

  13. Thermal-Hydraulic Experimental Testing of the Myrrha Wire-Wrapped Fuel Assembly

    Kennedy, G., Van Tichelen, K., Julio, P., Di Piazza, J. & Doolaard, H., 20 Jun 2019, In: Nuclear Technology. p. 1-12 12 p.

    Research output: Contribution to journalArticlepeer-review

  14. Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

    Van Tichelen, K., Kennedy, G., Mirelli, F., Marino, A., Toti, A., Rozzia, D., Cascioli, E., Keijers, S. & Planquart, P., 12 Jun 2019, In: Nuclear Technology. p. 1-14 14 p.

    Research output: Contribution to journalLiterature reviewpeer-review

  15. Development of the HEXACOM Facility for Characterising the Heat Transfer Performance of the MYRRHA PHX in LBE

    Rozzia, D., Kennedy, G., Mirelli, F. & Van Tichelen, K., 19 Mar 2019, SESAME international workshop. Unknown, p. 1-13 13 p.

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

  16. Towards Validated Prediction with RANS CFD of Flow and Heat Transport in a Wire-wrap Fuel Assembly

    Roelofs, F., Uitslag-Doolaard, H., Dovizio, D., Blaz, M., Shams, A., Bertocchi, F., Martin, R., Julio, P., Di Piazza, I., Kennedy, G., Van Tichelen, K., Obabko, A. & Merzari, E., 19 Mar 2019, SESAME international workshop. Unknown, p. 1-11 11 p.

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

  17. 2018
  18. 3.4 - Operational aspects of experimental liquid metal facilities

    Kennedy, G., Di Piazza, I. & Bassini, S., 5 Dec 2018, Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. WP - Woodhead Publishing, p. 127-145 19 p.

    Research output: Contribution to report/book/conference proceedingsChapterpeer-review

  19. Instrumentation of a lead-bismuth eutectic cooled nuclear fuel assembly using fibre bragg gratings for characterizing the flow-induced vibrations

    De Pauw, B., Geernaert, T., Berghmans, F., Kennedy, G. & Van Tichelen, K., 2 Jul 2018, Advanced Photonics 2018 BGPP, IPR, NP, NOMA, Sensors, Networks, SPPCom, SOF): OSA Technical Digest . OSA - The Optical Society of America, p. 1-2 2 p. BM3A.3

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

  20. 2017
  21. Characterizing Flow-Induced Vibrations of Fuel Assemblies for Future Liquid Metal Cooled Nuclear Reactors Using Quasi-Distributed Fibre-Optic Sensors

    De Pauw, B., Kennedy, G., Van Tichelen, K., Geernaert, T., Thienpont, H. & Berghmans, F., 22 Aug 2017, In: Applied Sciences. 7, 13 p.

    Research output: Contribution to journalArticlepeer-review

  22. 2015
  23. Experimental investigation of the pressure loss characteristics of the full-scale MYRRHA fuel bundle in the COMPLOT LBE facility

    Kennedy, G., Van Tichelen, K. & Doolaard, H., 1 Sep 2015, 16th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). 13 p.

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

ID: 40932