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Technische Universität München

Fachzeitschriften

| 2018 | 2017| 2016 | 2015 | 2014 | 2013 | 2012 | 2011 | 2010 | 2008 | 2007 | 2005 | 2003 | 2002 | 1999 | 1998 | 1997 | 1996 | 1995

2018

  1. Al Issa, S., Macian-Juan, Droplets Entrainment Ratio in a PWR Hot-Leg Pipe Geometry, Nuclear engineering and design, 330C (2018), pp. 1-13. ISSN 0029-5493.

2017

  1. Al Issa, S., Macian-Juan, Image-processing of time-averaged interface distributions representing CCFL characteristics in a large scale model of a PWR hot-leg pipe geometry, Annals of nuclear energy 103(2017), pp 282–293.
     
  2. Al Issa, S., Macian-Juan, CFD validation of new Nu-Re correlations for the condensation of large steam bubbles directly injected into a flow in a vertical pipe and effects of bubbles forces upon momentum transfer, International Journal of Multiphase flows 94 (2017), pp 173–188.

2016

  1. Al Issa, S., MacIan-Juan, R. Experimental investigation and CFD validation of countercurrent flow limitation (CCFL) in a large-diameter PWR hot-leg geometry (2016) Journal of Nuclear Science and Technology, 53 (5), pp. 647-655 ISSN: 00223131.
     
  2. Al Issa, S., Macian R., CCFL Characteristics and Droplets and Droplets Entrainment 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).
     
  3. Knebel, M., Mercatali, L., Sanchez, V., Stieglitz, R., Macian-Juan, R. Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III) (2016) Annals of Nuclear Energy, 91, pp. 79-91 ISSN: 03064549.
     
  4.  Holt, L., Rohde, U., Kliem, S., Baier, S., Seidl, M., Van Uffelen, P., Macián-Juan, R. Investigation of feedback on neutron kinetics and thermal hydraulics from detailed online fuel behavior modeling during a boron dilution transient in a PWR with the two-way coupled code system DYN3D-TRANSURANUS (2016) Nuclear Engineering and Design, 297, pp. 32-43. Cited 1 time. ISSN: 0029549.
     
  5.  Cappia, F., Pizzocri, D., Schubert, A., Van Uffelen, P., Paperini, G.,  Pellottiero, D.,  Macián-Juan, R., Rondinella, V.V., “Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels”, Journal of Nuclear Materials, 480, 138-149.
     
  6. Cappia, F., Pizzocri, D.ac, Marchetti, M., Schubert, A., Van Uffelen, P., Luzzi, L., Papaioannou, D., Macián-Juan, R., Rondinella, V.V, “Microhardness and Young's modulus of high burn-up UO2 fuel”, Journal of Nuclear Materials, 479, 447-454.
     
  7. Frankl, M., Macián-Juan, R.,” Photonuclear benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII cross-section library ENDF7U using MCNPX”, Nuclear Science and Engineering, 183-1, 135-142.
     
  8. 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 2016, 4, 2497-2507.
     
  9. 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 2016, 1, 577-583, (2016).
     
  10.  Frankl, M., Macián-Juan, R., ” Photonuclear  benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII cross-section library ENDF7U using MCNPX”, Nuclear Science and Engineering,135-142, 183-1.

2015

  1. Geffray, C., Macián-Juan, R. Multi-scale uncertainty and sensitivity analysis of the TALL-3D experiment.  Nuclear Engineering and Design (2015, in Press) 0029-5493 (ISSN).
     
  2. G. Bandini, M. Polidori, A. Gerschenfeld, D. Pialla, S. Li, W.M. Ma, P. Kudinov, M. Jeltsov, K. Kööp, K. Huber, X. Cheng, C. Bruzzese, A.G. Class, D.P. Prill, A. Papukchiev, C. Geffray, R. Macian-Juan, L. Maa. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors.  Nuclear Engineering and Design (22-38, 2015) 0029-5493 (ISSN).
     
  3. Deubler, Miriam, Aleksandar Ivanov,Bert.L. Sjenitzer, Victor Sanchez, Robert Stieglitz,R. Macián-Juan. High-fidelity coupled Monte Carlo neutrontransport and thermal hydraulic simulations using Serpent 2/SUBCHANFLOW2.  Annals of Nuclear Energy (Vol.83, Sept.2015, Pages 352-375).
     
  4. Daeubler, M., Trost, N., Jimenez, J., Sanchez, V., Stieglitz, R., Macian-Juan, R. Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB (2015) Annals of Nuclear Energy, 84, pp. 31-44. ISSN: 03064549
     
  5. Bianco, A., Vitanza, C., Seidl, M., Wensauer, A., Faber, W., Macián-Juan, R. Experimental investigation on the causes for pellet fragmentation under LOCA conditions (2015) Journal of Nuclear Materials, 465, pp. 260-267. ISSN: 00223115
     
  6. Yamoah, S., Martínez-Cuenca, R., Monrós, G., Chiva, S., Macián-Juan, R. Numerical investigation of models for drag, lift, wall lubrication and turbulent dispersion forces for the simulation of gas-liquid two-phase flow (2015) Chemical Engineering Research and Design, 98, pp. 17-35. ISSN: 02638762
     
  7. Al Issa, S., Macian-Juan, R., Jimenez, G., Queral, C., Montero-Mayorga, J. Experimental investigation and flow visualization of steam condensation in a scaled IRWST-ADS simulator (2015) International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 10, pp. 8561-8574. ISBN: 9781510811843
     
  8. Dibon, M., Baldzuhn, J., Beck, M., Cardella, A., Köchl, F., Kocsis, G., Lang, P.T., Macian-Juan, R., Ploeckl, B., Szepesi, T., Weisbart, W. Blower Gun pellet injection system for W7-X (2015) Fusion Engineering and Design, 98-99, pp. 1759-1762. ISSN: 09203796

2014

  1. Al Issa, S.; Macian, R., Experimental investigation of countercurrent flow limitation (CCFL) in a large-diameter hot-leg pipe geometry: A detailed description of CCFL mechanisms, flow patterns and high-quality HSC imaging of the interfacial structure in a 1/3.9 scale of PWR geometry, Nuclear engineering and design 280 (2014) 550–563.  ISSN: 00295493.
     
  2. Dibon, M.a, Baldzuhn, J.a,  Beck, M.a, Cardella, A.b, Köchl, F.c, Kocsis, G.d, Lang, P.T.a, Macian-Juan, R.b,  Ploeckl, B.a,  Szepesi, T.d, Weisbart, W.a "Blower Gun pellet injection system for W7-X", Fusion Engineering and Design (2014).

  3. Calleja, M., Jimenez, J., Sanchez, V., Imke, U., Stieglitz, R., Herrero, J.J., Macián, R., “Investigations of boron transport in a PWR core with COBAYA3/SUBCHANFLOW inside the NURESIM platform”, Annals of Nuclear Energy 66, (2014).

  4. Calleja, M., Jimenez, J., Imke, U., Stieglitz, R., Herrero, J.J., Macián, R., “Implementation of hybrid simulation schemes in COBAYA3/SUBCHANFLOW coupled codes for the efficient direct prediction of local safety parameters”, Annals of Nuclear Energy 70, 216-229 (2014).

  5. Calleja, M., Sanchez, V., Jimenez, J., Herrero, J.J., Imke, U., Stieglitz, R., Macián, R., “Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks”, Annals of Nuclear Energy 71, 145-158 (2014).

  6. Al Issa, S., Weisensee, P., Macián-Juan, R.,”Experimental investigation of steam bubble condensation in vertical large diameter geometry under atmospheric pressure and different flow conditions”, International Journal of Heat and Mass Transfer 70, 918-929 (2014).

  7. Ferrari, La Torre, Pozzi, Silari. Monitoring reactions for the calibration of relativistic hadron beams. Nuclear Instruments and Methods in Physics Research A 763 Pages 177-183 (2014).

2013

  1. Ceuca, C.S., Macián-Juan, R., “Development of a 1 D hybrid HTC model using CFD simulations for the analysis of direct contact condensation as the driving force for water hammers”, Kerntechnik 78 (1), 25-30 (2013).

2012

  1. Mesado, C., Soler, A., Barrachina, T., Miró, R., García-Díaz, J.C., Macián-Juan, R., Verdú, G., “Uncertainty and Sensitivity of Neutron Kinetic Parameters in the Dynamic Response of a PWR Rod Ejection Accident Coupled Simulation”, Science and Technology of Nuclear Installations, 625878, (2012).

  2. A. Gomez-Torres, V. H. Sánchez-Espinoza, K. Ivanov, and R. Macián Juan, “DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters.Part I: Development, implementation and verification”, Annals of Nuclear Energy 48, 123-129 (2012).

  3. A. Gomez-Torres, V. H. Sánchez-Espinoza, K. Ivanov, and R. Macián Juan, “DYNSUB: A High fidelity coupled code system for the evaluation of local safety parameters. Part II: Comparison of the different temporal schemes implemented”, Annals of Nuclear Energy 48, 108-122 (2012).

2011

  1. P. Vinai, R. Macian-Juan, R. Chawla, “Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip”, Annals of Nuclear Energy, 38 (2–3), 358-370, (2011).

  2. S. Al Issa, S. and Macián, R., “A review of CCFL phenomenon Review Article”, Annals of Nuclear Energy, 38 (9), 1795-1819, (2011).

  3. Bertolotto, D., Manera, A., Macián, R., Chawla, R., “Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE Algorithm”, Nuclear Engineering and Design (2011).

  4. W. Barten, A. Jasiulevicius, O. Zerkak, R. Macián-Juan, “Analysis of the UMSICHT water hammer benchmark experiment 329 using TRACE and RELAP5”, Multiphase Science and Technology, 23 (1), 1-27, (2011).

2010

  1. Ánchel, F., Barrachina, T., Miró, R., Macián-Juan, R., “Uncertainty propagation and sensitivity analysis of coupled thermalhydraulic-neutronic nuclear power plant simulations: Influence of uncertainty in neutronic data”, Procedia - Social and Behavioral Sciences, 2 (6), pp. 7599-7600 (2010).

2008

  1. W. Barten, A. Jasiulevicius, A. Manera, R. Macián-Juan, O. Zerkak, “Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5“, Nuclear Engineering and Design 238 (4), 1129-1145 (2008).

  2. W. Barten, A. Manera, R. Macián-Juan, “On One- and Two-dimensional Standing Pressure Waves and one-dimensional travelling pulses using the US-NRC nuclear system Analysis Code TRACE“, Nuclear Engineering and Design 238 (10), pp. 2568-2582 (2008).

  3. de Crécy, A., Bazin, P., Glaeser, H. Skorek, T., Joucla, J., Probst, P., Fujioka, K., Chung, B.D., Oh, D.Y., Kyncl, M., Pernica, R., Macek, J., Meca, R., Macián, R., D’Auria, F., Petruzzi, A., Batet, L., Perez, M., Reventos, F., “Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme”,Nuclear Engineering and Design, 238 (12), 3561-3578 (2008).

2007

  1. Vinai, P., Macián-Juan, R., and Chawla, R., “A Statistical Methodology for the Quantification of Uncertainty in Best Estimate Code Physical Models”, Annals of Nuclear Energy 34 (8), 628-640 (2007).

  2. Macián, R., Zimmermann, M.A., and Chawla, R. “Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations”, Journal of Nuclear Science and Technology 44 (6), pp. 875-885 (2007).

2005

  1. Jasiulevicius, A. and Macián, R., “CHF Experiments in Single Tubes – TRACEv4.05 Code Validation”, ANS Transactions, 92, 430-431 (2005).

  2. Jasiulevicius, A., Zerkak, O. and Macián, R., “Loss of Residual Heat Removal System: TRACEv4.00 Simulation of a PKL Experiment”, ANS Transactions, 92, 442-443 (2005).

2003

  1. Macián, R., Coddington, P. and Stangroom, P., “Assessment of RETRAN-3D Boiling Models against Experimental Subcooled Boiling Tube Data”, Nuclear Technology, 142, 47-63 (2003).

2002

  1. Coddington, P., Macián, R., Zimmermann, M.A. and Chawla, R., “Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients”, Journal of Nuclear Science and Technology, 39(9), 972-985 (2002).

  2. Coddington, P. and Macián, R, “A Study Of The Performance of Void Fraction Correlations used in the Context of Drift-Flux Two-Phase Flow Models”, Nuclear Engineering and Design, 215, 199-216 (2002).

  3. Macián R. and Coddington, P., ”Simulation And Analysis Of Experimental Blowdown And Small Break Loss Of Coolant Scenarios With Retran-3D”, Nuclear Technology, 139, 185-204 (2002).

1999

  1. Macián R., Cebull, P., Coddington P. and Paulsen M., “Implementation of an improved interfacial mass and energy transfer model in RETRAN-3D”, Nuclear Technology, 128(2), 139 (1999).

  2. Ivanov K.N., Macián-Juan R., Irani A., and Baratta A.J., “Features and performance of a coupled three-dimensional thermal-hydraulics/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code”, Annals of Nuclear Energy, 26, 1407, (1999).

  3. Macián, R., “Development of new Models for the PWR Licensing Code RETRAN-3D at Swiss PSI”, Nuclear Europe World Scan, 3-4, 60, (1999).

1998

  1. Macián-Juan, R. and Mahaffy, J.H., “Numerical Diffusion and the Tracking of Solute Fields in System Codes: Part I. One-dimensional Flows”, Nuclear Engineering and Design, 179, 297 (1998).

  2. Macián-Juan, R. and Mahaffy, J.H., “Numerical Diffusion and the Tracking of Solute Fields in System Codes: Part II. Multi-dimensional Flows”, Nuclear Engineering and Design, 179, 321 (1998).

  3. Macián-Juan, R. and Mahaffy, J.H., “Numerical Diffusion and the Tracking of Solute Fields in System Codes: Part III. Application to a Boron Dilution Transient in the AP600”, Nuclear Engineering and Design, 179, 345 (1998).

1997

  1. Tyler, T.N., Macián, R. and Mahaffy, J. H., “Analysis of the return to power scenario following a LBLOCA in a PWR’, Nuclear Engineering and Design, 177(1-3), 189-197, (1997).

  2. Watson J., Ivanov K.N., Macián-Juan R., and Baratta A.J., “Cross Section Generation Methodology for Three-dimensional Transient Reactor Simulation”, Trans. Am. Nuc. Soc., 77, 175 (1997).

1996

  1. Tyler, T. N., Macián, R. and Mahaffy, J. H., “Analysis of a PWR LBLOCA without SCRAM”, Nuclear Safety, 37(2), 126 (1996).

1995

  1. Lider, S., Macián, R., Baratta, A., et al. “Simulation of BWR Stability Following an ATWS with Boron Injection Using TRAC-BF1 with One-dimensional Kinetics”, Nuclear Science Journal, 32, 42 (1995).

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