Julio Pacio

Research output

Research output per year 2020 2022 2023 2024

• 15 In-proceedings paper
• 4 Article
• 2 Special issue

Research output per year

Research output per year

Search results

• 2024

  Experiments and CFD for wire-wrapped fuel assembly blockages

  Roelofs, F., Mathur, A., Uitslag-Doolaart, H., Daubner, M., Liftin, K. & Pacio, J., 28 Aug 2024, 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14). Canadian Nuclear Society, 12 p.

  Research output › peer-review

• Factors influencing the behaviour of FBG sensors for temperature measurements

  Carlesi, T., Laboureur, D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., 2024, Proceedings Advanced Photonics Congress 2024: Signal Processing in Photonic Communications, SPPCom 2024. Optical Society of America (OSA), paper JTu1A.9

  Research output › peer-review

  Open Access

• Multi-scale coupled simulation of E-SCAPE at isothermal conditions

  Hussain, M. M. M. D., Pangukir, F. S. L., Visser, D., Stempniewicz, M. M., Roelofs, F., Pacio, J. & Van Tichelen, K., 27 Aug 2024, 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14). Vancouver, BC, Canada: Canadian Nuclear Society, 13 p.

  Research output › peer-review
• 2023

  Analysis of the Scaling between Model Experimental Facilities MYRRHABELLE and E-SCAPE and the MYRRHA reactor augmented by CFD

  Koloszar, L., Lopes, S., Faruoli, M., Planquart, P., Van Tichelen, K., Pacio, J. & Keijers, S., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) . American Nuclear Society, p. 1136-1149 14 p.

  Research output › peer-review

  Open Access

• Asymmetric decay heat removal in MYRRHA: experiments in the E-SCAPE facility

  Pacio, J., Serrano Diogo, R. & Van Tichelen, K., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20). American Nuclear Society, p. 2986-2999 14 p.

  Research output › peer-review

  Open Access

• Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

  Pangukir, F. S. L., Visser, D., Roelofs, F., Pacio, J. & Van Tichelen, K., 25 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). 2023 ed. American Nuclear Society, p. 5048-5057 10 p. 54467

  Research output › peer-review

  Open Access

• Direct numerical simulation of flow in a confined differentially heated cavity at low Prandtl numbers

  Oder, J., Alsailani, M., Munters, W., Laboureur , D. & Pacio, J., 25 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). American Nuclear Society, p. 1206-1218 13 p.

  Research output › peer-review

  Open Access

• Experimental analysis of natural convection in a differentially heated cavity

  Carlesi, T., Oder, J., Laboureur , D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., Aug 2023, Natural convection: International Heat Transfer Conference 17 . 2023 ed. Begell house Inc., Vol. IHTC-17. 10 p. (International Heat Transfer Conference; vol. IHTC-17).

  Research output › peer-review

• Experimental analysis of natural convection in a differentially heated cavity

  Carlesi, T., Laboureur , D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., 21 Nov 2023, In: EPJ Web of Conferences. 288, 8 p., 05002.

  Research output › peer-review

  Open Access

• Modeling of Table Top Primary Heat Exchanger Experiment RUN#5 by Means of the System Codes RELAP5 mod 3.3 and Flownex SE 8.4

  Rozzia, D., Potgieter, M., Cools, J., Van Loy, T., Kennedy, G., Pacio, J., Van Tichelen, K. & Fernandez, R., 2023, Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, p. 722-735 14 p. 40591. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).

  Research output › peer-review

  Open Access
• 2022

  Advanced thermal-hydraulic experiments and instrumentation for heavy liquid metal reactors

  Pacio, J., Van Tichelen, K., Eckert, S., Wondrak, T., Di Piazza, I., Lorusso, P., Tarantino, M., Daubner, M., Litfin, K., Ariyoshi, G., Obayashi, H. & Sasa, T., 1 Dec 2022, In: Nuclear Engineering and Design. 399, p. 1-15 15 p., 112010.

  Research output › peer-review

  Open Access

• Advanced thermal-hydraulic experiments and instrumentation for heavy liquid metal reactors

  Pacio, J., Van Tichelen, K., Eckert, S., Wondrak, T., Di Piazza, I., Lorusso, P. & Tarantino, M., 10 Mar 2022, (Accepted/In press) NURETH-19 - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: Brussels, Belgium, March 6 – 11, 2022. American Nuclear Society, p. 1-16 16 p. 19001

  Research output › peer-review

  Open Access

• Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)

  Pacio, J., Chen, S.-K., Chen, Y.-M. & Todreas, N., Mar 2022, In: Nuclear Engineering and Design. 388, 19 p., 111607+corrigendum 111846.

  Research output › peer-review

  Open Access

• Comparison o RANS and LES heat transfer results for a 19-rod bundle experiment with wire spaces cooled by lead bismuth eutectic

  Uitslag-Doolaart, H. J., Roelofs, F., Brockmeyer, L., Degroote, J., Dolfen, H., Di Piazza, I., Marinari, R., Pacio, J., Keijers, S. & Van Tichelen, K., 6 Mar 2022, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: (NURETH19). Belgium, Brussels: American Nuclear Society, 16 p.

  Research output › peer-review

• Conjugate heat transfer and boundary condition phenomena in rod bundle experiments with liquid metals

  Keijers, S., Fiore, S. A., Pacio, J. & Van Tichelen, K., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: NURETH19. 2022 ed. Mol, Belgium: SCK CEN, 16 p. 35892

  Research output › peer-review

  Open Access

• Experimental program for demonstrating the timely insertion of safety rods in MYRRHA

  Pacio, J., Lamberts, D. & Van Tichelen, K., 16 Nov 2022, 2022 Winter Post Meeting access. American Nuclear Society, p. 1-3 3 p.

  Research output › peer-review

  Open Access

• Experimental thermal-hydraulic R&D achievements and needs for MYRRHA

  Pacio, J., Van Tichelen, K., Kennedy, G., Iarmonov, M., Rozzia, D., Schuurmans, P. & Fernandez, R., Sep 2022, (Accepted/In press) Unknown. IAEA - International Atomic Energy Agency, p. 1-10 10 p. (Proceedings Series - International Atomic Energy Agency).

  Research output › peer-review

  Open Access

• Identification of open issues in the UCTD model and proposed improvements for uses in licensing

  Pacio, J., Chen, S.-K., Chen, Y.-M. & Todreas, N., 6 Mar 2022, NURETH-19 - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: Brussels, Belgium, March 6 – 11, 2022. American Nuclear Society, p. 1-16 16 p. 34453

  Research output › peer-review

  Open Access
• 2021

  Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data

  Pacio, J., Chen, S.-K., Chen, Y.-M. & Todreas, N., 11 Dec 2021, In: Nuclear Engineering and Design. p. 1-13 13 p., 111606.

  Research output › peer-review

  Open Access

• Experimental results from a high heat flux solar furnace with a molten metal-cooled receiver SOMMER

  Mueller-Trefzer, F., Niedermeier, K., Fellmoser, F., Flesch, J., Pacio, J. & Wetzel, T., 30 Apr 2021, In: Solar Energy. 221, p. 176-184 9 p.

  Research output › peer-review

  Open Access
• 2020

  Adventures in study of the pressure losses in wire-wrapped rod bundle arrays

  Todreas, N., Chen, S.-K. & Pacio, J., 15 Dec 2020, In: Nuclear Engineering and Design. 370, p. 1-5 5 p., 110910.

  Research output › peer-review

  Open Access