Paolo Di Marco: Resumè

PERSONAL DATA

Current position:

Associate Professor, Engineering Thermodynamics and Heat Transfer, Faculty of Engineering, University of Pisa.

Office address:

Dipartimento di Energetica, Universita' di Pisa, via Diotisalvi 2, 56126 PISA (I).

Tel. ++39-50-0502217107; FAX ++39-050-2217150, E-mail: dimarco@ing.unipi.it.

Home address:

via di Piaggetta 16, 56121, Pisa; Tel. ++39-050-25259

High School: Classical Studies, 1975.
Degree in Nuclear Engineering, cum laude, University of Pisa, March 1984.
Research Doctorate (Ph.D.) in "Nuclear Engineering Safety", University of Pisa, 1990.
Post-graduate courses: Short Course on Two-Phase Flow Fundamentals for Industrial Applications, Zurich, March 23-27, 1987. Physical modelling of gas-liquid flows, Pisa, May 21-26, 1990.

March 1984 - February 1986: external consultant, Dipartimento di Costruzioni Meccaniche e Nucleari, University of Pisa. Mechanichal and thermal-hydraulic design and construction of PIPER-ONE apparatus.
March 1986 - February 1989: Research Doctorate (Ph.D.), Nuclear Engineering Safety, Universita' di Pisa. Meanwhile: visiting research assistant (Feb. 88- Aug. 88) at Rensselaer Polytechnic Institute, Troy, NY, USA (Prof R.T. Lahey).
March 1989 - January 1990: external consultant, Dipartimento di Costruzioni Meccaniche e Nucleari, University of Pisa. PIPER-ONE research team.
February 1990 - November 1990: external consultant, Dipartimento di Ingegneria Chimica, University of Pisa. Measurements in two-phase and three-phase flows.
December 1990 - August 1994: research assistant, Dipartimento di Energetica, University of Pisa. Instructor in Thermodynamics and Heat Transfer.
September 1994 - February 2000: assistant professor, Engineering Thermodynamics and Heat Transfer, Faculty of Engineering, University of Pisa.
Since March 2000: associate professor, Engineering Thermodynamics and Heat Transfer, Faculty of Engineering, University of Pisa.

Entropic characterization of blowdown phenomena.
Heat transfer stability in transition boiling.
Counter-current flow limitation (CCFL): analysis of available correlations and of capability of advanced codes (RELAP5 and CATHARE).
PIPER-ONE research: experimental simulation thermal-hydraulic transients in nuclear boiling water reactors, and analyses with advanced codes and simplified models.
Linear and non-linear analysis of density-wave oscillations in boiling channels and systems.
Natural circulation in boiling loops.
Heat transfer with impinging jets.
Pool boiling with electric fields and/or in microgravity conditions.
Advanced thermal-hydraulic measurements: hot film anemometry; two and three-phase flowrate; void fraction.

This page is created and maintained by Paolo Di Marco.
Last modified on April 20, 2000