Diego Castelliti

Research output

Research output per year 2009 2019 2021

• 12 Article
• 9 In-proceedings paper
• 1 Book as author
• 1 Chapter
• 2 More
  • 1 Special issue
  • 1 Doctoral thesis

Research output per year

Research output per year

Search results

• 2021

  Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

  Pucciarelli, A., Toti, A., Castelliti, D., Belloni, F., Van Tichelen, K., Moscardini, M., Galleni, F. & Forgione, N., Apr 2021, In: Annals of nuclear energy. 153, p. 1-23 23 p., 107990.

  Research output › peer-review

  Open Access

• Thermo-mechanical behaviour of the MYRRHA core support structure

  Laulusa, A., Nietvelt, J., Fernandez, R., Castelliti, D. & Schyns, M., 1 Dec 2021, In: Nuclear Engineering and Design. 384, p. 1-23 23 p., 111451.

  Research output › peer-review

  Open Access

• Total loss of flow benchmark in CIRCE-HERO integral test facility

  Lorusso, P., Del Nevo, A., Narsisi, V., Giannetti, F., Caruso, G., Zwijssen, K., Breijder, P. A., Hamidouche, T., Castelliti, D., Rozzia, D. & Tarantino, M., 1 May 2021, In: Nuclear Engineering and Design. 376, p. 1-24 24 p., 111086.

  Research output › peer-review

  Open Access
• 2019

  Calculation tool for heat exchanger tube rupture in pool-type reactors

  Castelliti, D. & Lomonaco, G., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 2384-2397 14 p.

  Research output

• H2020 MYRTE CIRCE-HERO experimental campaign: Post-test activity and code validation

  Castelliti, D., Hamidouche, T., Lorusso, P. & Tarantino, M., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 5029-5042 14 p.

  Research output

• Immortal experimental loop at JAEA - Post-process and validation

  Castelliti, D., Watanabe, N., Obayashi, H., Sugawara, T., Sasa, T. & Nishihara, K., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 248-261 14 p.

  Research output

• LBE-cooled scaled Pool facility E-SCAPE: Results and applications for code validation

  Castelliti, D., Van Tichelen, K. & Mirelli, F., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 1837-1850 14 p.

  Research output

• MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO

  Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K. & Tarantino, M., 3 Nov 2019, In: Nuclear Engineering and Design. 353, p. 1-10 10 p., 110270.

  Research output › peer-review

  Open Access

• MYRRHA Primary Heat Exchanger Experimental Simulations on CIRCE-HERO

  Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Caruso, G., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K. & Tarantino, M., 19 Mar 2019, SESAME International Workshop Petten, The Netherlands, 19-21 March, 2019: Workshop paper. 2019 ed. Petten, The Netherlands: Unknown, p. 1-12 12 p.

  Research output › peer-review

• Thermal Hydraulic Aspects of Liquid Metal Cooled Reactors

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

  Research output › peer-review

• 2018

  4. System thermal hydraulics for liquid metals

  Forgione, N., Castelliti, D., Gerschenfeld, A., Polidori, M., Del Nevo, A. & Hu, R., 5 Dec 2018, Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. WP - Woodhead Publishing, p. 157-184 28 p.

  Research output › peer-review

  Open Access

• The MYRRHA reactor design and the Primary Heat Exchanger (PHX) tube rupture event analysis

  Castelliti, D. & Van den Eynde, G. (Peer reviewer), 23 Apr 2018, 176 p.

  Research output

• 2017

  Safety studies for the MYRRHA critical core with the SIMMER-III code

  Belloni, F., Castelliti, D., Schyns, M., Chen, X.-N., Li, T.-R., Gabrielli, F., Rineiski, A., Andriolo, L., Guo, L., Bubelis, E., Bandini, G. & Sarotto, M., 1 Dec 2017, In: Annals of nuclear energy. 110, p. 1030-1042 13 p.

  Research output › peer-review

  Open Access

• Shielding and activation calculations around the reactor core for the MYRRHA ADS design

  Ferrari, A., Mueller, S., Konheiser, J., Castelliti, D., Sarotto, M. & Stankovskiy, A., 25 Sep 2017, In: EPJ Web of Conferences. 153, p. 1-3 3 p., 05001.

  Research output › peer-review

  Open Access
• 2016

  A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle

  Castelliti, D. & Lomonaco, G., 15 Aug 2016, In: Nuclear Engineering and Design. 305, p. 179-190 12 p.

  Research output › peer-review

  Open Access

• Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models: Technical Paper / Special Issue on the RELAP5-3D Computer Code

  Castelliti, D. & Hamidouche, T., 1 Jan 2016, In: Nuclear Technology. 193, 1, p. 36-46 10 p.

  Research output › peer-review

• Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D models on steady state and PLOF transient

  Castelliti, D. & Hamidouche, T., 1 Jan 2016, In: Nuclear Technology. 196, 1, p. 36-46 11 p.

  Research output › peer-review

  Open Access
• 2015

  Safety analysis of the U reactor

  Castelliti, D., Van den Eynde, G., Van Tichelen, K. & Arien, B., Sep 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 4731-4744 14 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 6).

  Research output › peer-review
• 2013

  MYRRHA/FASTEF Safety Analysis in Sub-critical and Critical Mode

  Castelliti, D. & Arien, B. (Peer reviewer), 13 May 2013, NURETH-15 Book of Abstracts. Pisa, Italy, Vol. 1. p. 375-375

  Research output › peer-review

• Parametric and uncertainty study of a counter current LBE-water heat exchanger with trace and susa

  Jäger, W., Sánchez, V. & Castelliti, D., Aug 2013, 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012. 1 ed. ASME - The American Society of Mechanical Engineers, p. 565-572 8 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 2, no. 1).

  Research output › peer-review

  Open Access

• The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

  Sarotto, M., Castelliti, D. & Arien, B. (Peer reviewer), Aug 2013, In: Nuclear Engineering and Design. 265, p. 184-200

  Research output › peer-review

  Open Access
• 2012

  MYRRHA Primary Heat Exchanger design

  Castelliti, D. & Fernandez, R. (Peer reviewer), Feb 2012, Working Material - T. M. on Innovative HX and SG design for fast reactors. Vienna, Austria, Vol. 1. p. 1-16

  Research output › peer-review

• Neutronic characterization and decay heat calculations in the in-vessel fuel storage facilities for MYRRHA/FASTEF

  Castelliti, D., Malambu Mbala, E., Di Maria, S., Ottolini, M. & Sarotto, M., Dec 2012, In: Energy Conversion and Management. 64, 12, p. 522-529 8 p.

  Research output › peer-review

  Open Access
• 2011

  Neutronic assessment and criticality analysis of the in-vessel fuel storage facilities in the CDT project

  Di Maria, S., Ottolini, M., Sarotto, M., Martin-Fuertes, F., Vazquez, M., Malambu Mbala, E., Teles, P. P., Castelliti, D., Vaz, P., Reale, M., Mansani, L. & Baeten, P., Jan 2011, In: Fusion Science and Technology. 61, 1T, p. 98-301 4 p.

  Research output › peer-review

  Open Access
• 2009

  GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides

  Castelliti, D., Bomboni, E., Cerullo, N., Lomonaco, G., Parisi, C. & Arien, B. (Peer reviewer), 2 Mar 2009, In: Science and Technology of Nuclear Installations. 2009, 1, p. 1-8

  Research output › peer-review

  Open Access