Prof. Dr. Rafael Macián-Juan
Academic Career and Research Areas
Professor Macián-Juan, MSc in Energy Systems (1990), Polytechnic University of Valencia, Spain, MSc (1993) and PhD (1996) in Nuclear Engineering, Pennsylvania State University, USA, holds the Chair of the Department of Nuclear Engineering (NTech).
He has more than 20 years of experience in nuclear safety and the development and application of computer based methodologies for the analysis of nuclear systems. Professor Macián-Juan worked for ten years at the Paul Scherrer Institute (PSI), Switzerland, carrying out research and development in the areas of reactor thermal-hydraulics and coupled neutronics calculations and performing safety evaluations for the Swiss Nuclear Power Plants.
In 2007 he joined the TUM Department of Mechanical Engineering where he was appointed to the newly established Chair of the Department of Nuclear Engineering. Professor Macián-Juan has published more than 70 articles in refereed journals and peer-reviewed conference publications on nuclear engineering related subjects. The main areas of research carried out at NTech focus on nuclear safety research, experimental thermal-hydraulics, the medical application of radiation, and the nuclear reactor and nuclear fuel designs of the future.
Key Publications (all publications)
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. 2014; 70: 918-929.
Gomez-Torres A, Sánchez-Espinoza VH, Ivanov K, Macián-Juan R: “DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part I: Development, implementation and verification”, Annals of Nuclear Energy. 2012; 48: 123-129.
Al Issa S, Macián S, Macián R: “A review of CCFL phenomenon Review Article”. Annals of Nuclear Energy. 2011; 38 (9): 1795-1819.
Vinai P, Macian-Juan R, Chawla R: “A Statistical Methodology for the Quantification of Uncertainty in Best Estimate Code Physical Models”. Annals of Nuclear Energy. 2007; 34(8): 628-640.Abstract
Coddington P, Macian 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. 2002; 215: 199-216.Abstract