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Technische Universität München
Technische Universität München

Konferenzen

2016 | 2015 | 2014 | 2013 | 2012 | 2011 | 2010 | 2009 | 2008 | 2007 | 2006 | 2005 | 2004 | 2001| 2000 | 1999 | 1996 | 1995 | 1994 | 1993

2017

  1. ICONE25, DEVELOPMENT OF A MULTIPHYSICS APPROACH WITH ANSYS CFX AND PARCS, 2.-6. Jul. 2017, Zhuoqi Du, Marcus Seidl, Rafael Macián-Juan
     
  2. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, PRELIMINARY HYDRAULIC ANALYSIS OF THE DISTRIBUTION ZONE IN THE DUAL FLUID REACTOR CONCEPT, 3.-8. Sep. 2017, Xi'an China, Xiang Wang, Chunyu Liu, Rafael Macián-Juan
     
  3. WRFPM 2017 (2017 Water Reactor Fuel Performance Meeting), Mechanical Analysis of the Creep Deformation of a Row of Fuel Assemblies in a PWR Core, 10.-14. Sep. 2017, Jeju Island, Korea,         Andreas Wanninger, Marcus Seidl, Rafael Macián-Juan
     
  4. Al Issa, S., Macian R., Modelling of large steam bubbles condensation injected into flowing subcooled water using the inhomogeneous MUSIG approach, 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Xi’an, Shaanxi, China, Sept. 3-8, 2017, Paper 20460
     
  5. Al Issa S., Murase M., Tomiyama A., Hayashi K., and Macián-Juan R., On CCFL in COLLIDER test facility: CCFL results at PWR hot-leg pipe geometry with 190 mm diameter. 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Xi’an, Shaanxi, China, Sept. 3-8, 2017, Paper 21023. 

2016

  1. Al Issa, S., Macian R., CCFL Characteristics and Droplets and Droplets  Entrainment Ratio in a 1/3.9 Downscaled Model of a PWR Hot-Leg Pipe Geometry, 11th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-11) Gyeongju, Korea, October 9-13, 2016. (Paper No N11P0128).
     
  2. Andreas Wanninger, Marcus Seidl, Rafael Macián-Juan,Development of Computational Methods to Describe the Mechanical Behavior of PWR Fuel Assemblies, Jahrestagung Kerntechnik Annual Meeting on Nuclear Technology 2016, Hamburg, 10-12 Mai.
     
  3. Andreas Wanninger, Marcus Seidl, Rafael Macián-Juan, Screening sensitivity analysis of a PWR fuel assembly FEM structural model, Top Fuel 2016, Boise (USA), 11-16 September.
     
  4. Janin D., Seidl M., Soldevila M., Douce S., Brun E., Damian F., Poinot C., Macian R. , Hcsmr fuel assembly computations with apollo2  and Tripoli-4® codes, Proc. of ICAPP, Sun Valley Idano (USA), 1-5 Mai.
     
  5. Janin D., Seidl M., Soldevila M., Douce S., Arnaud G., Damian F., Poinot C., Macian R. , HCSMR fuel assembly optimization with APOLLO2  and Uranie codes, Proc. of PHYSOR, San Francisco (USA), 17-20 April.
     
  6. Andreas Wanninger, Armando Gómez Torres, Andrés Rodríguez Hernández, José Ángel González Vargas, XXVI Congreso Científico ININ-SUTIN, Acoplamiento externo del código termomecánico FINIX y el código de transporte AZTRAN, 5. - 7. Dezember.

2015

  1. A Papukchiev, C Geffray, M. Jeltsov, K. Kööp, P. Kudinov, D. Grischenko, Multiscale Analysis of Forced and Natural Convection including Heat Transfer Phenomena in the TALL-3D Experimental Facility,  The 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4; 08/2015.
  2. C. Geffray, R. Macián-Juan, A. Papukchiev, D. Grishchenko, P. Kudinov, Development of a Multi-Scale Thermal-Hydraulic Model of the TALL-3D Facility and Validation with Experimental Data, International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, France, May 2015.
  3. X. Wang, M. Seidl, R. Macian-Juan, Preliminary Analysis of Basic Reactor Physics of the Dual Fluid Reactor, 15720 ICAPP 2015), (ICAPP 2015), Nice, France, May 2015.
  4. C. Geffray,·R. Macián-Juan, A. Papukchiev, D. Grishchenko, P. Kudinov, Uncertainty and Sensitivity Analysis of the TALL-3D Experiment Using Thermal-Hydraulic Coupled Codes, International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, France, May 2015.
  5. J. I. Tijero-Cavia, R. Macián-Juan, M. Seidl, P. Van Uffelen, A. Schubert, S. Brémier, P. Poeml, Transuranus Burn-Up Extension For (Th,Pu)O2 Type Fuel In Light Water Reactors, Top Fuel 2015, Zürich, Switzerland 13-17 September 2015.
  6. X. He, M. Seidl, R. Macian-Juan, Simulation of Reactivity Initialized Transients at Different Power Levels for Molten Salt Reactor Using Modified TRACE, International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, France, May 2015.
  7. X. He, M. Seidl, R. Macian-Juan, Simulation of the System Dynamics for the Molten Salt Reactor Experiment Using Modified TRACE, , International Conference on Nuclear Engineering (ICONE23), Chiba, Japan, 17-21 May 2015.
  8. X. He, D. Zhuoqi, R. Macian-Juan, M. Seidl, The Risk-rewards Structure of Using Spent Nuclear Fuel in Molten Salt Reactor, 21st International Conference & Exhibition: " Nuclear Fuel Cycle for a Low-Carbon Future" (GLOBAL2015), Paris, France, 20-24 September 2015.
  9. F. Cappia, A. Schubert, P. Van Uffelen, D. Papaioannou, R. Macián-Juan, V.V. Rondinella, Micro-hardness and local properties of high burnup UO2 fuel, Top Fuel 2015, Zürich, Switzerland 13-17 September 2015.

2014

  1. Geffray, C. and Macian-Juan, R., “A Study of Different Approaches for Multi-Scale Sensitivity Analysis of the TALL-3D Experiment Using Thermal-Hydraulic Computer Codes”, 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), December 14-18, 2014 Okinawa, Japan. Paper NUTHOS10-1052.

  2. Geffray, C., Papukchiev, A, and Macian-Juan, R. “Multi-Scale Uncertainty and Sensitivity Analysis of the TALL-3D Experiment Using Thermal-Hydraulic Coupled Codes”, 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), December 14-18, 2014 Okinawa, Japan. Paper NUTHOS10-1103.

  3. Al Issa, S., Macian R., Experimental investigation and CFD validation of countercurrent flow limitation (CCFL) in a large-diameter hot-leg PWR geometry, 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) December 14-18, 2014 Okinawa, Japan. Paper NUTHOS10-1211.

  4. L. Holt, A. Schubert, J. van de Laar, P. Van Uffelen. Stand-alone modelling of the high burnup structure formation and burst release during design basis accidents. OECD Halden Reactor Project Enlarged Halden Programs, Group Meeting 07-12 September 2014, Norway.

  5. A. Bianca (E.ON), C. Vitanza (HP). Separate effects test on fuel fragmentation during LOCA. Halden Reactor Project Enlarged Halden Programs, Group Meeting 07-12 September 2014, Norway.

  6. Holt, L., Rhode, U., Seidl, M., Schubert, A., van Uffelen, P., Macián-Juan, R., Two-Way Coupling Between the Reactor Dynamics Code DYN3D and the Fuel Performance Code TRANSURANUS at Assembly Level, ICONE 22, Prague, Czech Rep., July (2014).

  7. Geffray, C., Macián-Juan, R., Multi-Scale 2D-Sensitivity Analysis of the TALL-3D Experiment, ICONE 22, Prague, Czech Rep., July (2014).

  8. Papukchiev, A., Jeltsov, M.,Geffray, C., Kööp, K., Kudinov, P., Macián-Juan, R., and Lerchl, G., Prediction of Complex Thermal-Hydraulic Phenomena Supplemented by Uncertainty Analysis with Advanced Multi-scale Approaches for the TALL-3D T01 Experiment, Probabilistic Safety Assessment and Management PSAM 12, Honolulu, Hawaii, June (2014).

  9. Ciriac, F., Ceuca, S.C., and Macián-Juan, R., CFD Simulation of horizontal Flow Regimes with the OpenFOAM, 45th Jahrestagung Kerntechnik May (2014).

  10. Albrecht, R., Walser, S., Roshan, P., and Macián-Juan, R., Optimized Nodalizationn for the BWR Stability Analysis with TRACE/PARCS., 45th Jahrestagung Kerntechnik May (2014)

  11. Wanninger, A., Seidl, M., and Macián-Juan, R., Understanding future Research Needs to better describe Fuel Assembly Bow in PWRs, 45th Jahrestagung Kerntechnik May (2014).

  12. Holt, L., Rhode, U., ,Seidl, M., Schubert, A., van Uffelen, P., ,Macián-Juan, R., Getting the Details of Fuel Rod Simulation in Reactor Safety Analysis right: performmance of the coupling DYN3D Transuranus for RIA, 45th Jahrestagung Kerntechnik May (2014).

  13. Dibon, M., Baldzuhn, J., Beck, M., Cardella, A., Köchl, F., Kocsis, G., Lang, P., Macián-Juan, R., Plöckl, B., Szepesi, T., and Weisbart, W., Blower Gun pellet injection system for W7-X, DPG Conference, Berlin, March 17-21 (2014).

  14. L. Capriotti, D. Papaioannou, S. Bremier and V.V. Rondinella, K. Inagaki, H.Ohta and T. Ogata, R. Macián-Juan "Post Irradiation Examination of Fast Reactor Metallic Fuel for Minor Actinides Transmutation", IYNC2014, Burgos, Spain (2014).

2013

  1. Ceuca, S.C., Macián-Juan, R., Validation of a hybrid surface renewaltheory based HTC model for the simulation of condensation induced water hammer, International Conference on Nuclear Engineering, ICONE21 July 29-August 2, Chengdu, China (2013).

  2. Al Issa, S., Macian R., Experimental investigation of CCFL in large diameter hot-leg geometry, Proceedings of the 21th International Conference on Nuclear Engineering ICONE21 July 29-August 2, Chengdu, China (2013).

  3. Al Issa S., Weisensee P., Experimental investigation of steam bubble condensation in flowing sub-cooled water with two different injection nozzle geometries, Proceedings of the 21th International Conference on Nuclear Engineering ICONE21 July 29-August , Chengdu, China (2013).

  4. Al Issa, S., Moreno-Prosper, M., Developing a procedure for calculation of bubble parameters, diameter, velocity, aspect ratio and path depending upon shadowgraph technique and high speed camera recordings for multiple bubbles and diluted bubbly flows, Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15, Pisa, Italy, May 12-17, (2013).

  5. Al Issa, S., Weisensee P., Experimental investigation of steam bubble condensation in flowing sub-cooled water in vertical large diameter geometry under atmospheric pressure, Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15, Pisa, Italy, May 12-17, (2013).

  6. Ceuca, C.S and Macian-Juan, R., Benchmark of Surface Renewal Theory based Heat Transfer Coefficient for the Simulation of Direct Contact Condensation in Pipes using the 1D and 3D Approach, Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15, Pisa, Italy, May 12-17, (2013).

2012

  1. C. S. Ceuca and R. Macián-Juan, “CFD Simulation Of Direct Contact Condensation With ANSYS-CFX Using Locally Defined Heat Transfer Coefficients”, International Conference on Nuclear Engineering, Proceedings, ICONE-20, 429-437 (2012).

2011

  1. C. S. Ceuca and R. Macián-Juan “Direct Contact Condensation in Horizontal Two-Phase Flow with OpenFOAM”, Open Source CFD International Conference (OSCIC), Paris (2011).

  2. Peña Monferrer C., Pellacani F., Chiva Vicent S., Miró Herrero R. and Macián Juan R., “A procedure for coupled CFD-Neutronic calculation using ANSYS CFX 12.1 and PARCS”, IV International Conference on Computational Methods for Coupled Problems in Science and Engineering, COUPLED PROBLEMS 2011, Kos Island, Greece, 20-22 June (2011).

  3. Peña Monferrer C., Pellacani F., Chiva Vicent S., Miró Herrero R., Barrachina Celda T. and Macián Juan R., “CFD-Neutronic coupled transient calculation of a simplified PWR fuel assembly using ANSYS CFX 12.1 and PARCS”, IV International Conference on Computational Methods for Coupled Problems in Science and Engineering, COUPLED PROBLEMS 2011, Kos Island, Greece, 20-22 June (2011).

  4. Peña Monferrer C., Pellacani F., Chiva Vicent S., Miró Herrero R., Barrachina Celda T. and Macián Juan R., “CFD-Neutronic coupled calculation of a quarter of a simplified PWR fuel assembly using ANSYS CFX 12.1 and PARCS”, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Ontario, Canada, 25-30 September (2011).

  5. Pellacani F., Chiva Vicent S. and Macian Juan R., “Implementation of a One-group interfacial area transport equation in a CFD code for the simulation of upward adiabatic bubbly flow”, 2011 International Nuclear Atlantic Conference, INAC 2011, Belo Horizonte, MG, Brazil 24-28 October (2011).

  6. Peña Monferrer C., Pellacani F., Chiva Vicent S., Miró Herrero R., Barrachina Celda T. and Macián Juan R., “CFD-Neutronic coupled calculation of a quarter of a simplified PWR fuel assembly including spacer pressure drop and turbulence enhancement” 2011 International Nuclear Atlantic Conference, INAC 2011, Belo Horizonte, MG, Brazil, 24-28 October (2011).

2010

  1. Pellacani F., Matturro Mestre S., Chiva Vicent S. and Macián Juan R., “CFD modeling of isothermal and non-isothermal bubbly flow in vertical condition using ANSYS CFX 12” V European Conference on Computational Fluid Dynamics, ECCOMAS CFD 2010 14-17 June Lisbon, Portugal (2010).

  2. Pellacani F., Matturro Mestre S., Chiva Vicent S. and Macian Juan R., CFD modeling of subcooled boiling in vertical bubbly flow condition using ANSYS CFX 12.18th International Conference on Nuclear Engineering, ICONE18, Xi’an, China, 17-21 May (2010).

  3. Jaeger, W., Sánchez-Espinoza, V.H., Macián-Juan, R., ‘On the uncertainty and sensitivity analysis of experiments with supercritical water with TRACE and SUSA’, International Conference on Nuclear Engineering, Proceedings, ICONE-4 (PARTS A AND B), 57-65, (2010).

2009

  1. Thieme, M., Tietsch, W., Macian, R., Hugo, V., Espinoza, S., ‘Post-test investigations of BFBT critical power tests with trace, International Conference on Nuclear Engineering, Proceedings, ICONE-3, 503-513, (2009).

  2. Juanas, J., Barrachina, T., Miró, R., and Macián-Juan, R., ‘Uncertainty and Sensitivity Analysis in The Neutronic Parameters Generation over the Coupled Thermalhydraulic-Neutronic Nuclear Power Plant Simulations‘, Int. Conf. on Mathematics, Computational Methods & Reactor Physics (M&C 2009), Saratoga Springs, New York, May 3-7, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009).

  3. Röttgen,C., Macián-Juan, R., A. Pautz, A., Zwermann, W., ‘Improvements and Applications of the Monteburns Depletion Code‘,Proc. of Jahrestagung Kerntechnik 2009, May 12-14, Dresden, Germany (2009).

  4. Türk, R., Murphy, M., Kröhnert, H., Macián-Juan, R., and Jatuff F., ‘Assessment of the Nuclide Concentration Estimates With CASMO-4E with Experimental Data for very High Burn-up UO2 And MOX Fuels‘, Proc. of Jahrestagung Kerntechnik 2009, May 12-14, Dresden, Germany (2009).

  5. Türk, R., Murphy, M., Kröhnert, H., Macián-Juan, R., and Jatuff F., ‘Long-Term Evaluation of the Isotopic Sources Of Neutrons in High Burn-Up Fuel With CASMO-4E‘, Proc. of Jahrestagung Kerntechnik 2009, May 12-14, Dresden, Germany (2009).

2008

  1. Vinai, P., Macian-Juan, R., Chawla, R., ‘Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom Turbine Trip‘, Proc. of PHYSOR 2008, September 14-19, Interlaken, Switzerland (2008).

2007

  1. Jasiulevicius, A., Zerkak, O. and Macian-Juan, R., ‘Simulation of ROSA-V Test 6.2 Using Trace’, Proceedings of ICONE-15, Nagoya, Japan, April 21-26 (2007).

  2. Jasiulevicius, A. and Macian-Juan, R., ‘Assessment of the CHF Models In TRACE Code against Rod Bundle Experimental Data’, Proceedings of ICONE-15, Nagoya, Japan, April 21-26 (2007).

2006

  1. Barten, W., Jasiulevicius, A., Zerkak, O., Macian-Juan, R. ‘Analysis of UMSICHT Water Hammer Benchmark Tests: Results from PSI Using TRACE and RELAP5’, 7th International Conference on Hydroinformatics, Nice, France, September 4-8, (2006).

  2. Jasiulevicius, A., Macian-Juan, R., ‘Predictions Of Critical Heat Flux In Annular Pipes With TRACE V4.160 Code’, Paper 89253, Proc. of ICONE-14, Miami, FL, USA, July 17-20 (2006).

  3. Jasiulevicius, A., Macian-Juan, R., ‘STEADY STATE FILM BOILING HEAT TRANSFER SIMULATED WITH TRACE V4.160’, Paper 89494, Proc. of ICONE 14, Miami, FL, USA, July 17-20 (2006).

  4. Vinai, P., Macian-Juan, R. and Chawla, R., ‘A Methodology for the Quantification of Uncertainty in Best Estimate Code Physical Models’, Paper 6093, Proc. of ICAPP ’06, Reno, NV USA, June 4-8, (2006).

  5. Jasiulevicius, A., Macian-Juan, R., ‘Predictions of Critical Heat Flux in Long Heated Tubes with The TRACEv4.160 Code’, Paper 6298, Proc. of ICAPP ’06, Reno, NV USA, June 4-8, (2006).

  6. Jasiulevicius, A., Zerkak, O., Macian-Juan, R., ‘Investigation of Heat Transfer Mechanisms under Shutdown Plant Conditions with TRACEv4.160, Paper 6281, Proc. of ICAPP ’06, Reno, NV USA, June 4-8, (2006).

2005

  1. Jasiulevicius, A., Macian, R., Coddington,P. and Sanchez, J., ‘Assessment of TRACE Code against CHF Experiments’, NURETH-11, Avignon, France, October 2-6 (2005).

2004

  1. Macian, R., Zimmermann, M.A. and Chawla, R., ‘Assessment of CASMO-4 Predictions of the Isotopic Inventory of High Burn-Up MOX Fuel’, Proceedings of PHYSOR-4, Chicago, USA, April  24-29, (2004).

  2. Macian, R., Zimmermann, M.A. and Chawla, R., ‘Uncertainty Analysis Applied to Fuel Depletion Calculations’, Proceedings of PHYSOR-4, Chicago, USA, April 24-29, (2004).

2001

  1. Macian, R. and Nechvatal, L., ‘Best Estimate Analysis of The Thermal Expansion Scenario During Shutdown in a PWR’, Proceedings of ICONE-9, Nice, France, April 8-12, 2001.

2000

  1. Macian, R., Aounallah, Y., Coddington, P., Stangroom, P., ‘Assesment Of RETRAN-3D snd VIPRE-02 Void Prediction against Experimental Transient Data’, Proceedings of ICONE-8, Paper # 8283, April 2-6, Baltimore, MD ,USA, (2000).

  2. Macian, R. and Coddington, P., ‘Assessment of RETRAN-3D against Experimental Loss Of Coolant Scenarios’, Proceedings of ICONE-8, Paper # 8281, April 2-6, Baltimore, MD, USA, (2000).

1999

  1. Macian R., Cebull, P., Coddington P. and Paulsen M., ‘Implementation of a New Interfacial Mass and Energy Transfer Model in RETRAN-3D’, Proceedings of NURETH-9, San Francisco, CA, USA, October 3-8, (1999).

1996

  1. 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).

  2. Ivanov, K.N., Macian, R., Baratta, A.J., et al., ‘TMI MSLB Analysis using TRAC-PF1 Coupled with Three-dimensional Kinetics”. Proceedings of ICONE-4, New Orleans, LA, USA, March 10-13 (1996).

1995

  1. Macian, R., Tyler, T. and Mahaffy, J.H., ‘Large Break Loss of Coolant Accident Analysis Using TRAC-PF1 and Three Dimensional Kinetics’, Proceedings of NURETH-7, Saratoga Springs, NY, September (1995).

  2. Ivanov, K.N., Macian, R., Baratta, A.J., Irani, A., Folsom, J.W., Trikouros, N.G., ‘TMI MSLB Analysis Using TRAC-PF1 Coupled with Three-dimensional Kinetics’, Proceedings of the ANS Winter Conference, San Francisco, CA, November (1995).

1994

  1. Lider, S., Macian, R., Baratta, J. A., et al. "Simulation of BWR Stability Following an ATWS with Boron Injection Using TRAC-BF1 with One-dimensional Kinetics", Proceedings of the 4th. International Topical Meeting on Nuclear Thermal-Hydraulics, Operations and Safety. Taipei. April (1994).

1993

  1. Macian, R., et al., ‘Modeling of the LOCA and Post-LOCA Steam Generator Heat Release with WCOBRA-TRAC’. Steam Generator Thermal-Hydraulics Session. 29th National Heat Transfer Conference. Atlanta, GA. August (1993).

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