- Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS) Workshop, Cambridge (USA), 13-15 September, Papukchiev Angel (GRS), Geffray Clotaire (TUM)
A. Bianca, M. Seidl, W. Faber (E.ON), C. Vitanza (Halden) and R. Macián-Juan (TUM). Untersuchungen zur Brennstofffragmentierung während des Kühlmittelverluststörfalls. Fachtag zu aktuellen Themen rund um das Brennelement, Karlsruher Institut für Technologie, Campus Nord, FTU-Aula, 01-02 April (2014).
Al Issa, S., Macian R., Experimental Investigation and CFD validation Of CCFL in large diameter hot-leg geometry. CFD German Network Meeting, GRS, Garching, 19-20 March (2014).
Al Issa S., Weisensee P., Macián-Juan R., Experimental investigation of steam bubble condensation in flowing sub-cooled water, CFD German Network Meeting, GRS, Garching, 19-20 March (2014).
Geffray, C. and Macián-Juan, R., Multi-Scale Uncertainty and Sensitivity Analysis of the TALL 3D Facility with ATHLET – ANSYS CFX, CFD German Network Meeting, GRS, Garching, 19-20 March (2014).
Ceuca, S.C. and Macián-Juan, R., CFD-Simulation of Direct Contact Condensation as the Driving Force for Water Hammer, CFD German Network Meeting, GRS, Garching, 19-20 March (2014).
Yamoah, S., Martínez, R., Chiva, S. and Macián-Juan, R., Adiabatic two-phase flow modeling in vertical pipes using the homogeneous MUSIG model in ANSYS-CFX, CFD German Network Meeting, GRS, Garching, 19-20 March (2014)
Papukchiev,A., Lerch, G., Geffray, C., Macián-Juan, R., Jeltsov,M., Kööp, K., and Kudinov, P., Coupled 1D-3D Thermal-Hydraulic Simulations Of A Liquid Metal Experiment Supplemented By Uncertainty And Sensitivity Analysis, OECD/NEA & IAEA Workshop: "Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation", Zürich, Switzerland, September (2014).
Presentation at the German CFD User´s Group, ‘Towards a Coupling Methodology for CDF-Thermal-hydraulics and 3D Neutron Kinetics‘, October (2009).
Presentation at E.ON Kernenergie, ‘Best Estimate Analysis with Uncertainty Evaluation in Nuclear Safety‘, Hannover, Germany, November 10 (2008).
Presentation for United Bank of Switzerland (UBS) Forum, ‘Nuclear Power in the XXI Century Challenges and Opportunities‘,Frankfurt, Germany, November 11 (2008).
Seminar Nukleare Energieerzeugung at FZK, ‘The Role of Best Estimate Analysis with Uncertainty Evaluation in Nuclear Safety‘, Karlsruhe, June (2008).
Macian, R., Coddington, P. and Stangroom, P., ‘Assessment of RETRAN-3D Boiling Models against Experimental Subcooled Boiling Tube Data’, Proceedings of the 10th. International RETRAN Meeting, Jackson, WY, USA, October 14-17, (2001).
Mahaffy, J.H., and Macian, R., ‘Recent Advances in Two-phase Flow Numerics’, NUREG/CP-0159, Proceedings of the OECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements, Annapolis, MD, USA, November 5-8, (1996).
Ivanov, K., Macian, R., and Baratta, A., ‘Analysis of Reactivity Transients Using a Coupled Three-dimensional Thermal-hydraulic Kinetic Code’, Proceedings of the CSNI Meeting on Boron Dilution Transients, State College, PA, USA, October 18-20, (1995).
Macian, R., ‘CATHARE Simulation of Some of the FLECHT SEASET Steam Generator Separate Effect Test’, STR/LML/EM/94-225. Centre D'Etudes Nucleaires de Grenoble Report. Grenoble (1994).
Macian, R., Rueda, T., Verdu, G., et al. "Technical Specifications Based on Fiability Goals. Evaluation of STIs", 25th Annual Meeting of the Spanish Nuclear Society. Alicante (Spain), October (1989).
Rueda, T., Macian, R., Verdu, G. et al., "Technical Specifications Based on Reliability Goals II. Evaluation of AOTs", 25th Annual Meeting of the Spanish Nuclear Society. Alicante (Spain), October (1989).