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204

Nuclear Engineering

Prof. Dr.

Rafael

Macián-Juan

Contact

www.ntech.mw.tum.de sekretariat@ntech.mw.tum.de

Phone +49.89.289.15621

Management:

Prof. Dr. Rafael Macián-Juan, Director

Adjunct Professor

Prof. Dr. Antonino Cardella

Administrative Staff

Dipl.-Ing. (FH) Margitta Franke

Petra Popp-Münich

Research Scientists

Dr.-Ing. Suleiman Al Issa

Dr. rer. nat. Götz Ruprecht

Prof. Dr. Konrad Czerski

Daniel Weißbach, M.Sc.

M.Sc.-Ing. Du Zhuoqi

Dipl.-Ing. Clotaire Geffray

Jose Tijero, M.Sc.

Xiang Wang, M.Sc.

M.Sc.-Ing. Chunyu Liu

Dipl.-Ing. Andreas Wanninger

Maria E. de Rego Melo, M.Sc.

Soobeen Yum, M.Sc.

Yuanwei Cao, M.Sc.

External Ph.D. Students

M.Sc.-Ing. Felix Bold

Luca Cappriotti, M.Sc.

M.Sc.-Ing. Claudius Hammann

M.Sc.-Ing. Dennis Janin

M.Sc.-Ing. Ovidiu Melinte

Dipl.-Ing. K. Stammüller

Technical Staff

Andreas Borowski

Research Focus

■■

Thermal-hydraulic and neutronic

analysis of current and advanced

nuclear systems

■■

Reactor dynamics

■■

Nuclear fuel behavior

■■

Experimental two-phase flow

■■

Radiation transport and radiation

protection

■■

Medical applications of radiation

■■

The development and application of

uncertainty analysis methodologies

Competence

■■

Safety analysis for nuclear systems and

fuel behavior

■■

Two-phase flow experimental

measurements

■■

Monte Carlo-based radiation transport

and radiation dosimetry calculations

■■

Single and two-phase flow

computational fluid dynamics

■■

Nuclear reactor dynamics

■■

Molten salt reactor technology

Infrastructure

■■

Thermal-hydraulic two-phase flow

laboratory

■■

Computer laboratory with state-of-the-

art nuclear safety codes

Courses

■■

Introduction to Nuclear Energy

■■

Fundamentals of Nuclear Engineering

■■

Applications of Radiation to Medicine,

Research and Industry

■■

Fundamentals of Thermalhydraulics in

Nuclear Systems

■■

Advanced and Future Nuclear Reactor

Systems

■■

Radiation and Radiation Protection

■■

Nuclear Fusion Technology

■■

Nuclear Safety Seminar

■■

Use of System Analysis Codes in

Nuclear Safety

Master Program in Nuclear Engineering in

collaboration with the INSTN Institute in

Saclay, France

Selected Publications 2017

■■

Al Issa, S. and Macián-Juan, R., 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, 282-293, (2017)

■■

Al Issa, S., Macian-Juan, R., 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

Flow, 94, 173-188, (2017)

■■

Wang, X. and Macián-Juan, R.,

Comparative study of basic reactor

physics of the DFR concept using

U-PU and TRU fuel salts, 25th

International Conference on Nuclear

Engineering, Proceedings, ICONE,

Vol. 5, Shanghai; China; 2 July 2017

through 6 July; Code 131175, (2017)

■■

Du, Z., Seidl, M. and Macian-Juan, R.,

Development of a multiphysics

approach with ANSYS CFX and PARCS

for local analysis of neutron oscillation,

25th International Conference on

Nuclear Engineering, Proceedings,

ICONE, Vol 5, Shanghai; China; 2 July

2017 through 6 July; Code 131175,

(2017)

■■

Basualdo, J.R., Sánchez-Espinoza, V.H.,

Stieglitz, R., and Macián-Juan, R.,

Parcs-subchanflow-transuranus

multiphysics coupling for improved

pwr’s simulations, International

Congress on Advances in Nuclear

Power Plants, ICAPP 2017, Kyoto;

Japan; 24 April 2017 through 28 April;

Code 131581 (2017)