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Profilo di Cumo
  Nome: Cumo  -  Interventi: 12 - Ultima connessione: 13-03-2009 [10:39:33]

Curriculum di Maurizio Cumo

Curriculum vitae di Maurizio Luigi Cumo

Nato a Rimini il 27/3/1939, laureato in Ingegneria Nucleare al Politecnico di Milano a pieni voti, all'età di 22 anni, si trasferì a Roma presso il CNEN, Centro Studi Nucleari della Casaccia, Laboratorio Tecnologie Reattori.
Nel 1967 ottiene la Libera Docenza in Impianti Nucleari, nel 1969 diviene direttore del Laboratorio Tecnologie Reattori, nel 1970 viene incaricato del corso di Impianti Nucleari I presso la Facoltà di Ingegneria dell’Università di Roma.
Divenuto Ordinario di Impianti Nucleari dal 1976 presso tale  Facoltà, nel 1981 entra nel Consiglio di Amministrazione dell'ENEA e viene incaricato della presidenza della Commissione Tecnica per la Sicurezza Nucleare e la Protezione Sanitaria (DPR 185 del 13.2.64).
Nel 1983, presso la Facoltà di Ingegneria, costituisce l'Istituto di Impianti Nucleari (8 cattedre), che dirige fino al 1986.
L'anno successivo passa a dirigere la Scuola di Specializzazione in "Sicurezza Nucleare e Radioprotezione" di cui cura la trasformazione ed estensione in Scuola di Specializzazione in "Sicurezza e Protezione Industriale" e quindi in “Sicurezza e Protezione”, ora Master di 2° livello.

Dal 1983 è socio benemerito e fondatore dell’Unione Termofluidodinamica Italiana (UIT).

Presso la Facoltà di Ingegneria dell’Università “Sapienza”  nel 2002 diviene presidente del nuovo Consiglio d’Area di Ingegneria Energetica e Nucleare, incarico rinnovato per il triennio 2005-2008.
Dal 1997 è coordinatore anche del Dottorato di Ricerca in Energetica.

Durante questo periodo svolge diversi altri incarichi. Sin dall’inizio è membro del Comitato Scientifico del Programma Finalizzato Energetica del CNR; nel 1983 diviene presidente dell’Associazione Nazionale di Ingegneria Nucleare (ANDIN) e, successivamente, della commissione energia nucleare dell’UNI, UNICEN.
Nel 1990, diviene vice-presidente dell’UNI, ente normativo italiano, per un triennio.

Nel 1989 è eletto nel comitato direttivo dell’International Solar Energy Society (ISES) e nel 1991 diviene membro del comitato esecutivo dell’International Centre for Heat and Mass Transfer (sede in Ankara). Nel 2002 diviene presidente dell'ICHMT per il quadriennio 2002-2006 (www.ichmt.org).

Nel 1994 gli viene assegnato il premio internazionale Italgas per l’energia e la medaglia Luikov per i risultati ottenuti nelle ricerche di  termofluidodinamica

Dalla costituzione, fa parte della Commissione Grandi Rischi della presidenza del Consiglio dei ministri, Protezione Civile, di cui ora è membro della sezione “Rischio Industriale, Nucleare e Chimico”). Nel 1992 è eletto socio dell’ Accademia Nazionale delle Scienze, detta dei XL (www.accademiaxl.it) e della Academia Scientiarum et Artium Europaea (www.european-academy.at), di cui nel 2005 diviene membro del Senato, in rappresentanza dell’Italia.  Nel 2002 è eletto presidente della Società Italiana per il Progresso delle Scienze (www.sipsinfo.it).

Nel 2007 è eletto vice presidente dell’Associazione Italiana Nucleare, AIN.
ed è  chiamato nel Consiglio Scientifico della Fondazione Luigi Einaudi.
Nel 2008 è confermato vice presidente dell’ATI, Associazione Termotecnica Italiana.

Altri impegni accademici lo vedono membro della New York Academy of Sciences, della Professors World Peace Academy, della Assembly for International Heat and Mass Transfer Conferences, della Assembly of World Conferences on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics.

Nel biennio 2000-2002 diviene presidente della Società per la Gestione degli impianti nucleari italiani, SOGIN che ha il compito di smantellare le quattro vecchie centrali elettronucleari.

Nel 2002 è nominato dal Commissariat à l'Energie Atomique francese presidente del Consiglio Scientifico Internazionale della Direzione Energia Nucleare, incarico rinnovato per  il quadriennio 2006-2010.
Nel secondo semestre 2003 ha svolto l’incarico di presidente del Gruppo Questioni Atomiche della Unione Europea e nel 2004 è diventato membro del Consiglio Tecnico Scientifico dell'Euratom per il quadriennio 2004-2008, incarico riconfermato per il quadriennio 2008-2012 (art. 134 EURATOM)

Nel 2006 ha avuto l’incarico dall’ENEL di presiedere la Commissione Internazionale di Sicurezza Nucleare per i costruendi reattori MOCHOVCE 3&4.

Nel 2007 è stato rinominato presidente della SOGIN, società che nel frattempo ha ricevuto dallo Stato il compito di eseguire il decommissioning anche di quattro impianti del ciclo del combustibile nucleare eserciti dall’ENEA.

Nel maggio 2008 è stato eletto presidente della EAES – European Atomic Energy Society.

Pubblicazioni

La sua attività scientifica si è sviluppata secondo varie linee ed è documentata da più di 220 pubblicazioni:

• una linea di ricerca di base in termofluidodinamica, scambio termico in convezione naturale e forzata, in monofase e bifase (fenomeni del trasporto di calore e di massa);
• una linea di ricerca di base su particolari fenomeni di scambio termico e sui relativi meccanismi fisici, con particolare riguardo alle condizioni estreme (flussi termici critici, portate critiche);
• una linea di ricerca applicata sul comportamento termoidraulico di componenti di reattori nucleari;
• una linea di ricerca applicata sui sistemi nucleari, di contenuto soprattutto progettuale, per i nuovi reattori nucleari a sicurezza intrinseca (MARS), in cui l’evoluzione del progetto deve massimizzare l’esperienza operativa e nel contempo soddisfare i nuovi requisiti di sicurezza intrinseca e passiva;
• altre ricerche, svolte nell’ambito del Dottorato in Energetica, riguardano specifici settori dei sistemi energetici quali la cogenerazione elettricità-calore, le reti di teleriscaldamento, analisi di sicurezza dei gasdotti, tecniche di raccolta e confinamento della CO2, applicazioni del metodo MARKAL per analisi e scenari energetici, ecc.

I risultati di molte ricerche sono stati anche pubblicati, in forma concentrata, nei seguenti libri:

• Aspetti fondamentali dell'ebollizione (Edizioni CNEN, 1968)
• Note di Scambio Termico (Edizioni CNEN, 1968) - Elementi di Termotecnica del Reattore (Edizioni CNEN, 1969)
• Termotecnica Sperimentale - (Edizioni ENEA, 1982)
• Impianti Nucleari (Edizioni UTET, 1976 e 1986) e Edizioni Sapienza, 2008
• Thermal Hydraulics (Edizioni CRC, Boca Raton, Florida, 1988)
• Safety design criteria for industrial plants, Voll. I-II (CRC Press Inc. 1989)
• Thermal hydraulic design of components for steam generation plants (CRC Press Inc. 1990)
• Ingegneria dei Reattori Nucleari a Fusione (Edizioni ENEA, 1991)
• Nuclear Power Plant, volume del CATTID dell’Università La Sapienza per l’UNESCO, 1995, anche in versione CD ROM (distant learning package).
• Nuclear Plants Decommissioning - Università di Roma "La Sapienza" - Scuola di Specializzazione in Sicurezza e Protezione - 2002 – ISBN 88-900812-0-1
• Impianti e installazioni industriali ad alto rischio - Università di Roma "La Sapienza" - Scuola di Specializzazione in Sicurezza e Protezione – 2003 – ISBN 88-900812-2-8


Altre Pubblicazioni

FULL-SIZE HEAT TRANSFER TESTS ON SUPPORTO OF STRAIGHT TUBES ONCE-THROUGH SODIUM HEATED STEAM GENERATORS
RT/CNEN-1963

NUMERICAL CALCULATION OF EXTENDED SURFACE EFFICIENCY
7th Nat. Heat Transfer Conference AIChE-ASME, Cleveland, Ohio,
1964

DIRECT HEAT TRANSFER IN PRESSURE-SUPPRESSION SYSTEMS
NR-18 – 1964

BASIC ASPECTS AND HEAT EXCHANGE IN NUCLEATE BOILING
RT/CNEN - 1964

SOME ASPECTS OF FREE CONVECTION BOILING HEAT TRANSFER
3rd Int. Heat Transfer Conference - Chicago, 1966

THE INFLUENCE OF GEOMETRY ON CRITICAL HEAT FLUX IN SUBCOOLED BOILING
9th Nat. Heat Transfer Conf. - AIChE-ASME, Seattle, Washington, 1967

HEATED WALL-DROPLET INTERACTION FOR TWO-PHASE FLOW HEAT TRANSFER IN LIQUID DEFICIENT REGION
Symposium on Two-Phase Flow Dynamics (EURATOM), Eindhoven, The Netherlands, 1967

BUBBLE DYNAMICS IN NUCLEATE BOILING
Colloque Euromech n. 7, Grenoble, 1968

NOTES ON DROPLET HEAT TRANSFER
10th Nat. Heat Transfer Conference AIChE-ASME, Phyladelfia, 1968

SOME REMARKS ABOUT HEATED WALL-DROPLETS INTERACTION
Invited Lecture at the Siberian Section of the Academy of Sciences of the U.S.S.R., Novosibirks, May 20, 1968

BUBBLE FLOW UP TO THE CRITICAL PRESSURE
11th nat. Heat Transfer Conference ASME-AIChE, Minneapolis,
Minn. August 3-6, 1968
ASME Paper n. 69 HT-30, 1969

REMARKS ABOUT THE "ONCE-THROUGH" PROBLEM
1968 ANS Winter Meeting, Washington D.C.

SOME OBSERVATIONS ON HEAT TRANSFER TO FREON 12 IN THE NEAR CRITICAL REGIME
1969 CRYOGENIC Engineering Conference, UCLA, Los Angeles, California, June 16-18, 1969

THEORETICAL REMARKS ABOUT POST DRY-OUT HEAT TRANSFER WITH TWO-PHASE FLOW MIXTURES
1969 International Seminar Heat and Mass Transfer in flows with Separated Regions, Herceg Novi - Jugoslavia, Sept. 1-13, 1969

POST BURN-OUT HEAT TRANSFER UP TO THE CRITICAL PRESSURE
A.N.S. - Winter Meeting, San Francisco - Nov. 30-Dec. 4, 1969

POST DRY-OUT HEAT TRANSFER WITH STEAM WATER MIXTURES
Transactions of A.N.S. - Vol. 12, pp. 8O9-910, Nov. 1969

ONCE-THROUGH STEAM GENERATORS WITH TWISTED-TAPES
American Nuclear Society, 16th Annual Meeting, June 8-July 2, 1970
Los Angeles, California

TWO-PHASE HIGHLY DISPERSED FLOWS
American Nuclear Society, 16th Annual Meeting, June 28-July 2,1970 - Los Angeles, California

A TENTATIVE EMPLOY OF THE INFORMATION THEORY IN TWO-PHASE HIGHLY DISPERSED FLOWS
La Termotecnica, Vol. XXIV - n. 4, 1970

QUALITY INFLUENCE IN POST-BURNOUT HEAT TRANSFER
HTFMI International Congress of Fluid Dynamics
Naval postgraduate School, Monterey, California, June 1970
International Journal Heat Mass Transfer - Vol. 14 - pp. 483÷489, 1971

HEAT TRANSFER IN THE LIQUID DEFICIENT REGIME
European Two-Phase Flow Group Meeting - Milan, June 1970

A PHOTOGRAFIC STUDY OF TWO-PHASE, HIGHLY DISPERSED FLOWS
European Two-Phase Flow Group Meeting - Milan, June 1970

FORCED CONVECTION HEAT TRANSFER AND BURNOUT MEASUREMENTS WITH TWISTED TAPES
European Two-Phase Flow Group Meeting - Milan, June 1970

POST-BURNOUT HEAT TRANSFER AND THERMODYNAMIC DISEQUILIBRIUM UP TO THE CRITICAL PRESSURE
Fourth Int. Heat Transfer Conference - Versailles, Paris, Aug.31,1970

POST BURNOUT HEAT TRANSFER
Panel on Heat and Mass Transfer in Nuclear Power Plants - Vienna, September 1970

MEASUREMENT OF THE EFFECT OF TWISTED TAPES ON THE FORCED- CONVECTION HEAT TRANSFER AND BURNOUT IN HEAT EXCHANGERS
Nuclear Science and Engineering - Vol. 46 - n. 1, October 1971

ANOMALIES IN POST DRY-OUT HEAT TRANSFER WITH STEAM WATER MIXTURES
European Two-Phase Flow Group Meeting, Risö, June 9-12, 1971
ANS Annual Meeting, Boston, June 13-17, 1971

THE INFLUENCE OF CURVATURE IN POST DRY-OUT HEAT TRANSFER
European Two-Phase Flow Group Meeting, Risö, June 9-12, 1971
International Journal for Heat and Mass Transfer, Vol. 15, 1972

ON TWO-PHASE HIGHLY DISPERSED FLOWS
All-Union (XV Siberian) Thermophysical Seminar, Novosibirsk,
May 22-26, 1972
ASME-AIChE National Heat Transfer Conference Atlanta, August 5-8-1973

THE INFLUENCE OF TWISTED TAPES IN SUBCRITICAL, ONCE-THROUGH VAPOUR GENERATORS IN COUNTER FLOW
27° ATI National Meeting - Napoli, September 27÷28, 1972   
1973 ASME-AIChE National Heat Transfer Conf., Atlanta, Ga., Aug. 5÷8, 1973
ASME Paper 73 HT-56

PREDICTION OF BURN-OUT POWER WITH FREON UP TO THE CRITICAL PRESSURE
European Two-Phase Flow Group meeting, Rome, June 6-8, 1972
27° ATI National Meeting, Naples, September 27-29, 1972

PRELIMINARY REMARKS ON EMERGENCY COOLING OF L.W.R.
28° ATI National Meeting, Turin September, 1973
European Two-Phase Flow Group meeting, Bruxelles June 4-7,1973

ON THE DETERMINATION OF THE LEIDENFROST POINT WITH SPRAYS OF WATER AND LOW-BOILING ORGANICS
ASME-AIChE Heat Transfer Conference, Atlanta, Ga, August 5÷8,1973

AN OUT OF PILE FACILITY FOR HEAT TRANSFER TESTS OF NUCLEAR PLANT COMPONENTS PROTOTYPES
"Il Calore", 1973

AN EXPERIMENTAL STUDY ON HEAT TRANSFER IN LONG. SUBCRITICAL ONCE-THROUGH STEAM GENERATORS
International Meeting on Reactor Heat Transfer, Karlsruhe, October
9-11, 1973

HYPERCRITICAL ONCE-THROUGH GENERATORS IN COUNTER FLOW WITH AND WITHOUT TWISTED TAPES
European Two-Phase Flow Group Meeting, Bruxelles, June 4÷7, 1973
1st International Heat Transfer Conference, Iasi, Romania, October 1973

A BURN-OUT CORRELATION TO SCALE WATER WITH FREON
19° Nuclear Meeting of Rome, 1974
European Two-Phase Flow Group Meeting, Harwell, June 3, 1974

POST BURN-OUT EXERCISE: COMPARISON OF  EXPERIMENTAL DATA
European two-Phase Flow Group Meeting, Harwell, June 3, 1974 

A BURN-OUT CORRELATION FOR ONCE-THROUGH L.M.F.B.R. STEAM GENERATORS
European two-Phase Flow Group Meeting, Harwell, June 3, 1974 

BURN-OUT POWER IN ONCE-THROUGH STEAM GENERATORS
5th International Heat Transfer Conference, Tokyo, Sept.3÷7, 1974

BOILING HEAT TRANSFER IN L.M.F.B.R. STEAM GENERATORS
CNEN Report RT/ING(74)17

HEAT TRANSFER TO DRY AND SUPERHEATED STEAM IN ONCE-THROUGH GENERATORS FOR L.M.F.B.R.'s
CNEN Report RT/ING(74)18

POST BURN-OUT HEAT TRANSFER (Attainable Precision Limits of the Measured Coefficient)
Cnen Report RT/ING(74)24

HEAT TRANSFER IN SUB-CRITICAL ONCE-THROUGH STEAM GENERATORS
Polska Akademia Nauk - National Heat Transfer Simposium - Jablonna (Warsaw) - 255-28 November,  - 1974
Archiwum Thermodinamiki i Spalania n. 4, Vol. 6, 1975

DIRECT AND INDIRECT HEATING EFFECT IN THE DNB TESTS FOR SODIUM HEATED STEAM GENERATORS FOR L.M.F.B.'s
1975 International Seminar, Dubrovnik, August 25÷30, 1975 -
International Centre for Heat and Mass Transfer

FULL SCALE TESTS AND THERMAL DESIGN CORRELATIONS FOR COILED ONCE-THROUGH STEAM GENERATORS
AIChE Symposium Series, Vol. 73 n. 164 - 1975
30° ATI National Meeting, Cagliari, Sept. 24÷27, 1975

A DESIGN CORRELATION FOR PRESSURE DROPS IN COILED, ONCE-THROUGH STEAM GENERATORS
European Two-Phase Flow Group Meeting, Grenoble, June 1976

ON TWO-PHASE THERMAL BOUNDARY LAYERS ALONG HEATED WALLS
30° ATI National Meeting, Cagliari, Sept. 24÷27, 1975
European Two-Phase Flow Group Meeting, Grenoble June 1976
NATO Advanced Study Institute, Istanbul, August 16÷17, 1976

BOILING SUBLAYERS ALONG HEATED WALLS
Nato Advanced Study Institute, Istanbul, August 16÷27, 1976
Two-Phase Flow and Heat Transfer Symposium, October 18÷20, 1976, Fort Lauderdale, Florida, USA

UP-FLOW AND DOWN FLOW BURNOUT
Two-Phase Flow and Heat Transfer Symposium, October, 18÷20, 1976 - Fort Lauderdale, Florida, USA

SUBCOOLED BOILING CORRELATION FOR THE THERMAL DESIGN OF COMMERCIAL STEAM GENERATORS
La Termotecnica, Vol. 31, n. 4, 1977

TEMPERATURE CONTROLLED AND HEAT FLUX CONTROLLED SYSTEMS
La Termotecnica n. 6, June 1977

DESIGN R.  D., AND MANIFACTURE OF THE COMPONENTS OF SECONDARY CIRCUITS FOR FAST SODIUM POWER PLANTS
IAEA Conference, Vienna, April 1978

THE INFLUENCE OF INCLINATION ON CHF IN STEAM GENERATORS CHANNELS
European Two-Phase Flow Group Meeting, Stockholm, May 29, 1978

QUALITY INFLUENCE ON DNB IN CROSS FLOW THROUGH BUNDLES
European Two-Phase Flow Group meeting, Stochkolm, May, 29, 1978
34 ATI National Meeting - Palermo 8÷12, 1979

HEAT TRANSFER IN CONDENSING JETS OF STEAM IN WATER (PRESSURE SUPPRESSURE SYSTEMS)
International Heat Transfer Conference, August 1978,Toronto

SUBCOOLED AND BULK BOILING CORRELATIONS FOR THERMAL DESIGN OF STEAM GENERATORS
International Heat Transfer Conference, August 1978, Toronto

TRANSIENT CRITICAL HEAT FLUX IN LOSS OF FLOW ACCIDENTS (L.O.F.A.)
Bruxelles Conference on the Safety of Nuclear Reactors, October 1978
International Journal Multiphase Flow, Vol. 4, pp. 495-509, 1978

NUCLEAR TRAINING AND EDUCATION IN ITALY
European Nuclear Society Conference, Hamburg May 6-11, 1979

SAFETY ASPECTS OF LWR's THERMOHYDRAULICS
European Nuclear Society Conference, Hamburg May 6-11, 1979

LOW-TEMPERATURE NUCLEAR HEAT UTILIZATION STUDIES
European Nuclear Society Conference, Hamburg May 6-11, 1979  

HEAT TRANSFER AND PRESSURE DROP IN ONCE-THROUGH STEAM GENERATORS
5th All-Union Heat and Mass Transfer Conference, Minsk, URSS, 1979

ON THE LIMITING CRITICAL QUALITY AND THE "DEPOSITION CONTROLLED" BURN-OUT
European Two-Phase Flow Group Meeting, Ispra, June 3÷6, 1979
34  ATI National Meeting - Palermo, October 8÷12, 1979

PRELIMINARY REMARKS ON JET IMPINGEMENT AND JET FLOW CONFIGURATIONS
18th International I.A.H.R. Congress, Cagliari, Sept. 10÷14, 1979

EXPERIMENTAL ADVANCES ON BOILER HEAT TRANSFER
2nd International Conference on Boiler Dynamic and Control in Nuclear Power Stations, BNES, Bournemouth, Oct. 23÷25, 1979

SINGLE AND TWO-PHASE CROSS FLOWS THROUGH TUBE BUNDLES
CNEN Report RT/ING(79)30, 1979 

ON DNB LOCATION WITH AXIALLY DISUNIFORM HEAT PROFILES: AN EXPERIMENTAL CONTRIBUTION
CNEN Technical Report - RT/ING(79) 21 - 1979
34 ATI National Meeting - Palermo, October  8÷12, 1979

QUALITY INFLUENCE ON THE DEPARTURE FROM NUCLEATE BOILING IN CROSS FLOWS THROUGH BUNDLES
NUCLEAR TECHNOLOGY n. 3, Vol. 49, August 198O

FULL SCALE TESTS ON AXIAL PROFILE HEAT FLUX INFLUENCE ON THE CRITICAL QUALITY IN PWR STEAM GENERATORS
International Seminar on Nuclear Reactor Safety - ICHMT - Dubrovnik, Sept. 1980

TWO-PHASE FLOWS IN SHELL AND TUBES BANKS
35° ATI National Meeting, Saint Vincent, Sept. 16÷19, 1980

INFLUENCE OF FLOW OBSTRUCTIONS ON THE DNB LOCATION IN SIMULATED FUEL BUNDLES
35° ATI National Meeting, Saint Vincent, Sept. 16÷19, 1980

EXPERIMENTAL REMARKS ON "SPUTTERING" PHENOMENA AND DROPLET GENERATION IN FALLING FILM REWETTING
ANS-ASME, International Meeting on Nuclear Reactor Thermalhydralics, Saratoga, N.Y., October 6÷8, 198O

ON THE DNB LOCATION WITH AXIALLY DISUNIFORM HEAT FLUX PROFILES AND FLOW OBSTRUCTIONS: AN EXPERIMENTAL CONTRIBUTION
ANS-ASME-NRC International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Saratoga Springs, N.Y., Oct. 5÷8, 1980

SOME ADVANCES IN THE THERMAL HYDRALICS OF REACTOR COMPONENTS
Keynote Address to the ANS-ASME-NRC International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Saratoga Springs, N.Y., Oct. 5÷8, 1980

REALISIERBARKEIT UND WIRTSCHAFTLICHKEIT DER FERNWARMETRANPORTATLINIEN AUS KKW IN ITALIEN
22 Kraftwarkestechnisches kolloquium Warme aus Kernenergie, Dresden, November 25÷26, 1980

STATE OF THE ART REVIEW OF RECENT ADVANCES IN NUCLEAR REACTOR SAFETY STUDIES
CNEN Report RT/ING(80)26

PRELIMINARY REMARKS ABOUT JET FORCES EXPERIMENTAL INVESTIGATION
CNEN Report RT/ISP(81)/17, November 1981

THERMODYNAMIC DISEQUILIBRIUM IN THE CRITICAL FLOW OF SUBCOOLED LIQUIDS
36° ATI National Meeting, Viareggio, Oct. 5÷9, 1981
NUCLEAR TECHNOLOGY - Vol. 60 - pp. 137÷142, 1983

OBSERVATIONS ON THE IMPINGEMENT OF DROPLETS ON HEATED WALLS IN EMERGENCY COOLING
36° ATI National Meeting, Viareggio, Oct. 5÷9, 1981

CRITICAL FLOWS AND JET FORCES
European Two-Phase Flow Group Meeting, Paris, June 2÷4, 1982

POST DRY-OUT HEAT TRANSFER IN UNCOVERED CORE ACCIDENTS
European Two-Phase Flow Group Meeting, Paris, June 2÷4, 1982

UNBOUNDED CRITICAL FLOWS AND JET FORCES
Nato Advanced Research Workshop on: Two-Phase Flows and Heat Transfer - München, Aug. 31-Sept. 3, 1982

UNCOVERED CORE HEAT TRANSFER AND THERMAL NON-EQUILIBRIUM
7th International Heat Transfer Conference, München Sept. 6÷10, 1982

CRITICAL FLOW JETS INVESTIGATIONS FOR ENGINEERING APPLICATIONS
3rd Multi-Phase Flow and Heat Transfer Meeting, Univ. of Miami, April 18÷20, 1983

TWO-PHASE BOUNDARY LAYERS IN CRITICAL FLOWS
European Two-Phase Flow Group Meeting, Zurich, June 14÷16, 1983

METASTABILITY DELAYS IN CRITICAL FLOWS
European Two-Phase Flow Group Meeting, Zurich, June 14÷16, 1983
38° ATI Nat. Meeting, Bari, Sept. 27 - Oct. 2, 1983

FLOODING CONDITIONS IN FALLING FILM REWETTING
European Two-Phase Flow Group Meeting, Zurich, June 14÷16, 1983
38° ATI Nat. Meeting - Bari, Sept. 29 - Oct. 2, 1983

TWO-PHASE JET FLOWS AND FORCES
IAEA Specialists' Meeting/workshop on "Experimental and Modelling Aspects of Small-Break LOCA"
Budapest, Hungary, Oct. 3÷7, 1983

PHYSICAL INSIGHT IN THE EVALUATION OF JET FORCES IN LOSS OF COOLANT ACCIDENTS
5th Int. Meeting on Thermal Nuclear Reactor Safety, Karlsruhe, Germany, Sept. 10÷13, 1984

THE OPPORTUNITY OF MULTI-PURPOSE NUCLEAR REACTORS FOR DEVELOPING COUNTRIES WITH PARTICULAR REGARD TO DESALINATED WATER PRODUCTION
Study Week on: Energy for Survival and Development - Rome, Pontificiae Academiae Scientiarum - June 11÷14, 1984

EXPERIMENTAL ANALYSIS OF THE FLOW INSIDE A CHANNEL IN POST DRY-OUT CONDITIONS
39° ATI Nat. Meeting, L'Aquila, Sept. 12÷14, 1984

EFFECT OF INLET WATER DISTRIBUTION AND OF LENGTH ON FLOODING TEST CONDITIONS
39° ATI Nat. Meeting, L'Aquila, Sept. 12÷14, 1984

MULTI-PURPOSE, SUPER-SAFE, SMALL REACTORS: AN INTERESTING POSSIBILITY FOR THE ARAB WORLD
Progresso e Tradizione: proposte per un programma di sviluppo - Rimini, Centro Pio Manzù - October 16, 1984

A COMPUTATION METHOD FOR MASS FLOWRATE PREDICTIONS IN CRITICAL FLOWS OF INITIALLY SUBCOOLED LIQUIDS IN LONG CHANNELS
Heat and Technology Report - Vol. 3 - n. 3/4 - 1985

DIRECT CONTACT CONDENSATION OF STEAM ON SLOWLY MOVING WATER
European Two-Phase Flow Group Meeting - Southampton, June 1985
U.I.T. - Palermo, June 1985
3rd International Conference on Reactor Thermal Hydraulics -  Newport, Rhode Island - October 15÷18, 1985
Nuclear Engineering and Design - Vol. 96 - pp. 21÷31, 1986  
Wärme und Staffünbertragung -n. 21 - pp. 169÷180,  1987   

TWO-PHASE FLOW MODELS IN UNBOUNDED TWO-PHASE CRITICAL FLOWS
European Two-Phase Flow Group Meeting - Southampton, June 1985
U.I.T., Palermo, June 1985
3rd International Conference on Reactor Thermal Hydraulics, Newport, Rhode Island, October 15÷18, 1985
Reprinted from Nuclear Engineering and Design - 1986

X-RAYS ANALYSIS IN UNBOUNDED TWO-PHASE CRITICAL FLOWS
Specialists Meeting on Small Break Loca Analyses in LWRs, Pisa, June 23÷27, 1985

ITALIAN ACTIVITIES FOR QUALITY DEVELOPMENT
The 1st Conference of the Asia-Pacific Quality Control Organization
The 3rd Asia-Pacific Congress for Quality Control
Beijing, China, 21÷25 October, 1985

FLOODING EXPERIMENTS IN A RECTANGULAR GEOMETRY
Energia Nucleare - December, 1985
Heat and Technology - Vol. 4 - n. 1, 1986

DIRECT CONTACT CONDENSATION OF SUPERHEATED STEAM ON WATER
3rd Int. Conference on Reactor Thermal Hydraulics - October 15÷18, 1985 - Newport, Rhode Island
Nuclear Engineering and Design - Jan. 1986
European Two-Phase Flow Group Meeting - Münich - June 1986
International Journal Heat and Mass Transfer - Vol. 30/3, 1987

STEADY-STATE TWO-PHASE FLOW AND HEAT TRANSFER
Ispra Courses “Thermohydraulic Problems Related to PWR Safety”
Ispra, February 24÷ March 7, 1986

REASSESSMENT OF FORCED CONVECTION HEAT TRANSFER CORRELATIONS FOR REFRIGERANT-12
Energia Nucleare - April 1986 - Vol. 3 - n. 1

CRITICAL FLOWS IN NUCLEAR REACTOR SAFETY
II Latin American Congress on Heat and Mass Transfer - Sao Paulo - Brazil, May 12÷15, 1986

INHERENTLY SAFE, MEDIUM SIZE NUCLEAR PLANTS: THE MARS REACTOR
1986 Joint ASME/ANS Nuclear Power Conference - Philadelphia, Pa. July 20÷23, 1986

MARS: AN ADVANCED PROPOSAL FOR THE MARKET OF SMALL AND MEDIUM SIZE NUCLEAR POWER PLANTS
ENC 86 - Geneva, June 1÷6, 1986

CHF IN FLOW BOILING DURING PRESSURE TRANSIENTS
Enea Technical Report - July 1986

CRITICAL HEAT FLUX IN FLOW TRANSIENTS
VIII Int. Heat Transfer Conference - S. Francisco Aug. 17÷22, 1986 

FLOW TRANSIENTS EXPERIMENTS WITH REFRIGERANT 12
ENEA  Technical Report - March 1986 - RT/TERM(86)2
Revue Générale de Thermique n. 299 - Nov. 1986

CRITICAL FLOWS AND TWO-PHASE JETS RELATED TO LWR's SAFETY
"Scritti per Lucio Lazzarino" Ed. Pacini 1986

SAFETY ISSUES OF FISSION REACTORS IN WESTERN EUROPE - STATUS AND PERSPECTIVES
Int. Seminar on Worldwide Collaboration for Safe and Peaceful use of Nuclear Energy - Rome, Casale di Villa Madama, Nov. 6÷8, 1986

FORCED CONVECTIVE BOILING IN HIGH PRESSURE PARALLEL FLOW
Nuclear Engineering and Design 99 - 1987

A THEORETICAL MODEL OF DIRECT CONTACT CONDENSATION ON A HORIZONTAL SURFACE
Int. Journal Heat and Mass Transfer - Vol. 30 - n. 3 - 1987

MARS REACTOR: A PROVEN PWR TECHNOLOGY COMBINED WITH ADVANCED SAFETY REQUIREMENTS
Energia Nucleare - May÷Sept. 1987

NUCLEAR ENERGY IN ITALY
Nuclearnatechnologija - 4, 1987

CHF DURING FLOW RATE, PRESSURE AND POWER TRANSIENTS IN HEATED CHANNELS
Invited Lecture at "Transient Phenomena in Multiphase Flow" - Dubrovnik May 24÷29, 1987

THE INFLUENCE OF NON-CONDENSIBLE GAS ON TWO-PHASE CRITICAL FLOWS
European Two-Phase Flow Group Meeting, Trondheim June 1÷4, 1987
U.I.T. - 5th Nat. Congress - Torino June 24÷25, 1987
Int. Journal Multiphase Flow - Vol. 14 - N. 2 - April 1988

CRITICAL HEAT FLUX IN FLOW BOILING DURING POWER TRANSIENTS
ASME-AIChE NAT. Heat Transfer Conference, Pittsburg, P.A., Aug.1987
U.I.T. - 5th Nat. Congress - Torino June 24÷25, 1987

NUMERICAL METHODS FOR THE ANALYSIS OF FLOW AND HEAT TRANSFER IN SHELL-AND-TUBE HEAT EXCHANGERS WITH SHELL-SIDE CONDENSATION
NATO Advanced Study Institute on "Thermal Hydraulic Fundamentals and Design of Two-Phase Flow Heat Exchangers"
Povoa de Varzim - Portugal - July 6÷17, 1987  
   

SAFETY CHARACTERISTICS OF MARS NUCLEAR PLANT
1st Int.. Seminar on "Small and Medium-Sized Nuclear Reactors" - Lausanne - Aug. 24÷26, 1987

MARS II - A DESIGN IMPROVEMENT TO REDUCE CONSTRUCTION TIME AND COST
1st Int. Seminar on "Small and Medium-Sized Nuclear Reactors", Lausanne, Aug.24÷26, 1987

MARS NUCLEAR PLANT: AN ITALIAN PROPOSAL FOR AN “INHERENT SAFETY” NUCLEAR REACTOR
US DOE and Italian MICA - Energy Security - Alternative Oils
March 28÷30, 1988- Argonne, Illinois


THE INFLUENCE OF FLOW OBSTRUCTIONS ON FLOODING PHENOMENON IN VERTICAL CHANNELS
European Two Phase Flow Group Meeting, Bruxelles May 30-June 1, 1988
ENEA Technical Report - n. 3 - 1988 
Int. Journal Multiphase Flow - Vol. 15, pp. 227-239, 1989

BOILING HEAT TRANSFER IN COMPLEX GEOMETRY
Energia Nucleare - 5 - N. 1 - April, 1988

INHERENT SAFETY FEATURES IN THE MARS PLANT
International Topical Meeting on Safety of Next Generation Power Reactors
Seattle, Washington - May 1÷5, 1988 

AIR-WATER FLOODING EXPERIMENTS IN VERTICAL ROUND CHANNELS WITH OBSTRUCTIONS
European Two-Phase Flow Group Meeting, Bruxelles May 29÷June 1, 1988
1st World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, Dubrovnik, Sept. 4÷9, 1988

CHF IN MULTIPLE TRANSIENTS: FLOW RATE AND POWER SIMULTANEOUS VARIATIONS
European Two-Phase Flow Group Meeting, Bruxelles May 29÷June 1, 1988

FLOODING IN INCLINED PIPES WITH OBSTRUCTIONS
European Two-Phase Flow Group Meeting, Paris May 29÷June 1, 1988

TRANSIENT CHF IN FLOW BOILING DURING FLOW RATE AND THERMAL POWER SIMULTANEOUS VARIATIONS
European Two-Phase Flow Group Meeting, Bruxelles May 29÷June 1, 1988

CRITICAL HEAT FLUX PHENOMENA IN FLOW BOILING DURING STEP-WISE AND RAMP-WISE POWER TRANSIENTS
Revue Générale de Thermique - N. 317 - June 1988

A THEORETICAL AND EXPERIMENTAL STUDY OF TURBULENT THERMAL CONDUCTIVITY OF WATER IN DIRECT CONTACT CONDENSATION
3rd Eurotherm Seminar: Modeling of Nuclear and Advanced Heat Transfer Components - Bologna, June 14÷15, 1988

EXPERIMENTAL ACTIVITIES FOR NUCLEAR SAFETY AND PLANTS IMPROVEMENT IN ITALY
1st World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, Dubrovnik, Sept. 4÷9, 1988
Experimental Thermal and Fluid Science 1990 - 3-487÷507

DIRECT CONTACT CONDENSATION OF STEAM ON SUBCOOLED LIQUID JETS
2nd U.K. National Heat Transfer Conference, Sept. 14÷15, 1988

SOLAR ACTIVITIES IN ITALY
International Conference on Applications of Solar & Renewable Energy - Cairo, Egypt, March 19÷22, 1989

CRITICAL HEAT FLUX IN TRANSIENT FLOW BOILING DURING SIMULTANEOUS VARIATIONS IN FLOW RATE AND THERMAL POWER
Experimental Thermal and Fluid Science, 1989

A COMPREHENSIVE ANALYSIS IN DIRECT CONTACT CONDENSATION OF SATURATED STEAM ON SUBCOOLED LIQUID JETS
ENEA Technical Report, 1988
Int. J. Heat and Mass Transfer - Vol. 32 - 1989

CHF BEHAVIOUR DURING PRESSURE,  POWER AND OR FLOW RATE SIMULTANEOUS VARIATION
7th Eurotherm Seminar "Thermal non Equilibrium in Two-Phase Flow" - Rome, March 22÷24, 1989
Int. Journal Heat and Mass Transfer - Vol. 34, n. 3, pp. 723-738, 1991

NUCLEAR RISKS
CESVAM International Conference: Civil Defence System for the Mediterranean Area - Rome,  March 1÷13, 1989

SAFETY ANALYSIS OF MARS IV NUCLEAR PLANT
26th National Heat Transfer Conference - Philadelfia, Aug. 1989
Small & Medium-Sized Nuclear Reactors: you & your environment - Anaheim, California - August 21÷23, 1989

A THEORETICAL AND EXPERIMENTAL STUDY OF DIRECT CONTACT CONDENSATION ON WATER IN TURBULENT FLOW
Experimental Heat Transfer, Vol. 2 - pp. 129÷148, 1989

ANATRA - A COMPUTER CODE FOR TRANSIENT CRITICAL HEAT FLUX ANALYSIS WITH REFRIGERANT-12
ENEA Technical Report - Oct. 1989

PROBABILISTIC SAFETY ASSESSMENT OF MARS PLANT
Energia Nucleare - Anno 6 N. 2 - May-Sept. 1989

INNOVATIVE REACTORS: A PROPOSAL. THE MARS
(Multipurpose Advanced Reactor Inherently Safe)
International School of Physics "Enrico Fermi": "Status and Perspective of Nuclear Energy: Fission and Fusion
CXVI Course - Villa Monastero - Varenna - July 10÷20, 1990

THE INFLUENCE OF GEOMETRY ON FLOODING: CHANNEL LENGTH AND DIAMETER
International Heat Transfer Conference - Jerusalem, August 19÷24, 1990

CULTURAL, SOCIAL AND SPIRITUAL ASPECTS OF GLOBAL ENERGY ISSUES
Unesco - Strategic Energy Issues Round Table - Dubrovnik - 17÷22 September, 1990

EXPERIMENTAL ACTIVITIES FOR NUCLEAR SAFETY AND NUCLEAR PLANT IMPROVEMENT IN ITALY
Experimental Thermal and Fluid Science, 1990

NATURAL CIRCULATION FOR DECAY HEAT REMOVAL IN NUCLEAR PLANTS
Eurotherm Seminar No. 16: "Natural Circulation in Industrial Applications" - Pisa, Oct. 11÷12, 1990

MARS: ITALIAN PROPOSAL FOR "INHERENTLY SAFE" REACTORS
Nuclear Europe - N. 11/12, November-December 1990

PRELIMINARY REMARKS ON HIGH HEAT FLUX CHF IN SUBCOOLED WATER FLOW BOILING
Heat and Technology - Vol.  - n. 1-2, 1990

DIRECT CONTACT CONDENSATION OF STEAM ON DROPLETS
Int. Journal Multiphase Flow - Vol 17, n. 2, pp. 191-211, 1991

HYSTERESIS EFFECT IN FLOODING
Int. Journal Multiphase Flow - Vol. 17, n. 2, pp. 283-289, 1991

HYSTERESIS PHENOMENA IN SUBCOOLED FLOW BOILING OF WELL WETTING FLUIDS
European Two Phase Flow Group Meeting - Roma, 27÷29 May, 1991
Experimental Heat Transfer, Vol. 5 - pp. 253-275, 1992

BURNOUT AT VERY HIGH HEAT FLUXES
IX UIT National Congress - Pisa June 13÷14, 1991
Wärme und Stoffübertragung 27, 233-244  - 1992

EXPERIMENTAL INVESTIGATION ON HIGH HEAT FLUX CHF IN SUBCOOLED WATER FLOW BOILING
IX UIT National Congress - Pisa, June 13÷14, 1991

FLOW PATTERN RECOGNITION IN HEATED VERTICAL CHANNELS: STEADY AND TRANSIENT CONDITIONS
Experimental Thermal and Fluid Science, 4, 737÷746, 1991

FUNDAMENTAL ASPECTS OF WATER SUBCOOLED FLOW BOILING IN TUBES WITH AND WITHOUT TURBULENCE PROMOTERS
Enea Report - Dec. 1991

A REVIEW OF RECENT EXPERIMENTS AND PREDICTION ASPECTS OF BURNOUT AT VERY HIGH HEAT FLUXES
Energia Nucleare - Sept.-Dec. 1991

INNOVATIVE SYSTEMS AND COMPONENTS AIMED AT PROVIDING PWR’s WITH COMPLETELY PASSIVE EMERGENCY SHUTDOWN AND DECAY HEAT REMOVAL
IAEA - Technical Committee Meeting on Progress in Development and Design Aspects of Advanced Water-Cooled Reactors- Rome, Sept. 9÷12, 1991

SUBCOOLED WATER FLOW BOILING CHF WITH VERY HIGH HEAT FLUXES
Revue Générale de Thermique - n. 362 - Feb. 1992

AN EXPERIMENTAL STUDY OF CHF UNDER COMPLEX AND SIMULTANEOUS TRANSIENT CONDITIONS
Wärme und Stoffübertragung 27 - pp. 17÷28, 1992

A DATA SET OF CRITICAL HEAT FLUX OF BOILING R-12 IN UNIFORMLY HEATED VERTICAL TUBES UNDER TRANSIENT CONDITIONS
Experimental Thermal and Fluid Science - n. 5 - pp.78÷107, 1992

FLOODING IN INCLINED PIPES WITH OBSTRUCTIONS
Experimental Thermal and Fluid Science - Vol.5, No.1, Jan. 1992

CHF IN HIGHLY SUBCOOLED FLOW BOILING WITH AND WITHOUT TURBULENCE PROMOTERS
European Two-Phase Flow Group Meeting-Stockholm1÷3 June,1992

FORCED CONVECTIVE BOILING OF REFRIGERANT IN BINARY MIXTURES
European Two-Phase Flow Group Meeting - Stockholm 1÷3 June,1992
Int. Journal of Heat and Mass Transfer - Vol. 36, n. 13, 1993
4th International Symposium with Exibition on Heat Transfer - Beijing, Oct. 7÷11, 1996

NEW POSSIBILITIES FOR NUCLEAR POWER PLANTS
Flowers 92 - Florence, 7÷12 June, 1992

GENERAL ECONOMIC EVALUATION OF THE CONVERSION OF NUCLEAR WARHEADS INTO ELECTRIC POWER
International Symposium on Conversion of Nuclear Warheads for Peaceful Purposes
STES - Rome, Palazzo Doria, June 15÷17, 1992

SUBCOOLED FLOW BOILING CHF AT HIGH LIQUID VELOCITY
Heat Transfer - 3rd UK National Conference Incorporating
1st European Conference on Thermal Sciences
Birmingham, 14÷18 September, 1992

AN OUTLOOK TO POSSIBLE EVOLUTIONS OF REACTOR DESIGNS
ENS on the Fiftieth Anniversary of Fermi Reactor and on the Peaceful Applications of Nuclear Energy
Liege, 14÷16 October 1992

A MODEL FOR FLOODING PREDICTION IN CIRCULAR TUBES
Journal of Thermal Science - Int. Journal of Thermal and Fluid Sciences - Vol. 1, N. 3, 1992

ASSESSMENT OF CORRELATIONS AND MODELS FOR THE PREDICTION OF CHF IN SUBCOOLED FLOW BOILING
Energia Nucleare - Anno 9 - N. 3 - Settembre, Dicembre 1992
European Two-Phase Flow Group Meeting - Hannover, June 7÷19,1993
XI National Congress U.I.T- Milano  June, 24÷26 , 1993
International Journal Heat Mass Transfer, Vol. 37, No. 2, pp. 237-255, 1994

VISUALIZATION OF HYPERVAPOTRON EFFECT
Energia Nucleare - Anno 9 - N. 3 - Settembre, Dicembre 1992
Specialists’ Worksop on High Heat Flux Components Thermal-Hydraulics
Rome, Sept. 9÷11, 1992

HYSTERESIS EFFECT IN THE BOILING INCIPIENCE OF WELL WETTING FLUIDS
X UIT National Congress - Genova, June 25÷27, 1992 
  
WATER SUBCOOLED CHF FLOW BOILING IN TUBES WITH AND WITHOUT TURBULENCE PROMOTERS
X UIT National Congress - Genova, June 25÷27, 1992   
Nureth 6 - Topical Meeting on Nuclear Reactor Thermalhydraulics - Grenoble, 5÷8 October, 1993

ETHICAL ASPECTS IN WORLD ENERGY PROBLEMS
UNESCO Round Table "Strategic Energy Issues in China"
Beijing, February 16÷18, 1993

BURNOUT IN HIGHLY SUBCOOLED WATER FLOW BOILING IN SMALL DIAMETER TUBES
Int. Journal Heat Mass Transfer - Vol. 36, No. 5, pp. 1269-1285, 1993

INFLUENCE OF CHANNEL DIAMETER ON SUBCOOLED FLOW BOILING BURNOUT AT HIGH HEAT FLUXES
Int. Journal of Heat  Mass Transfer - Vol. 36, n. 13, 1993

EXPERIMENTAL RESULTS ON HIGH HEAT FLUX BURNOUT IN SUBCOOLED FLOW BOILING
Energia Nucleare - N. 1 - Gennaio-Aprile 1993

HYPERVAPOTRON TECHNIQUE IN SUBCOOLED FLOW BOILING CHF
Experimental Thermal and Fluid Science, 1993

CRITICAL HEAT FLUX IN UPFLOW CONVECTIVE BOILING OF REFRIGERANT BINARY MIXTURES
XI National Congress U.I.T- Milano 24÷26 Giugno, 1993
International Journal  Heat Mass Transfer - Vol. 37-pp. 1143÷1153, 1994

A REVIEW OF POOL AND FORCED CONVECTIVE BOILING OF BINARY MIXTURES
3rd World Conference on Experimental Heat Transfer Fluid Mechanics and Thermodynamics - Hololulu, 31 Oct.- 5 Nov. 1993
Experimental Thermal and Fluid Science, pp. 367÷381, 1994

ENHANCEMENT OF CHF WATER SUBCOOLED FLOW BOILING IN TUBES USING HELICALLY COILED WIRES
International Journal Heat  Mass Transfer - Vol. 37, No. 1, pp. 53-67, 1994

RATIONALIZATION OF EXISTING MECHANISTIC MODELS FOR THE PREDICTION OF WATER SUBCOOLED FLOW BOILING CRITICAL HEAT FLUX
International Journal Heat  Mass Transfer - Vol. 37 - Suppl. 1, pp. 347-360, 1994

ANALYSIS OF CHF LOCATION SENSIBILITY FOLLOWING HEAT FLUX AND MASS FLUX VARIATIONS
International Journal Heat Heat Mass Transfer - Vol 37 - No.7, pp. 1073÷1080, 1994

BASIC PRINCIPLES FOR NUCLEAR SAFETY
Workshop on Nuclear Reactors - Physics, Design and Safety
International Centre for Theoretical Physics - Trieste April 11÷May 13, 1994
Workshop on Nuclear Reactors - Physics, Design and Safety
International Centre for Theoretical Physics - Trieste,  April 15÷May 17, 1996

A MECHANISTIC MODEL FOR THE PREDICTION OF WATER SUBCOOLED FLOW BOILING CHF
European Two-Phase Flow Group Meeting, Piacenza 6÷8 June, 1994
XII National Congress of the Italian Union of Thermo-fluid dynamics (UIT) - L’Aquila, June 23÷24, 1994
Energia Nucleare - Maggio/Giugno 1994

DIRECT CONTACT EVAPORATION OF NEARLY SATURATED R 114 IN WATER
XII National Congress of the Italian Union of Thermo-fluid dynamics (UIT) - L’Aquila, June 23÷24, 1994
International Journal Heat Mass Transfer- Vol.38- No.8,1995

BENEFITS FOR THE ENVIRONMENT FROM THE CONVERSION OF NUCLEAR WARHEADS
International Congress Conversion of Nuclear Weapons and Underdevelopment: Effective Projects from Italy
Rome, July 4÷5, 1994

RECENT ACHIEVEMENTS IN SUBCOOLED WATER DNB AT VERY HIGH HEAT FLUXES
International Siberian Thermophysical Seminar
Devoted to the Memory of Academician S.S. Kutateladze
Novosibirsk, July 17÷20, 1994

DIRECT CONTACT BOILING OF IMMISCIBILE LIQUIDS
10th International Heat Transfer Conference - BRIGHTON 14÷18 August, 1994

REACTORS SAFETY ANALYSIS AND METHODS
Postgraduate Course on Energy Engineering - Module: Nuclear Power Plant
Produced by CATTID - Centro per le Applicazioni della Televisione e delle Tecniche di Istruzione a Distanza - University of Rome “La Sapienza” for Division of Engineering and Technology of UNESCO - Rome, 1994

INHERENT AND PASSIVE SAFE NUCLEAR REACTORS: STEPS TOWARDS A SECOND NUCLEAR GENERATION
1994 Fermi Lecture-New York,Columbia University,Jan.26 1995

RECENT ACHIEVEMENTS IN SUBCOOLED WATER DNB AT VERY HIGH HEAT FLUXES
Russian Journal of Engineering Thermophysics,1994, vol. 4, p.83

THE PREDICTION OF THE CRITICAL HEAT FLUX IN WATER-SUBCOOLED FLOW BOILING
International Journal Heat Mass Transfer - Vol. 38, No.6, 1995

A PROPOSED NEW DIRECTION IN THE DEVELOPMENT OF NUCLEAR ENERGY
International Journal of Global Energy Issues - page 31÷33- Vol. 7, Nos. 1/2, 1995

HEAT TRANSFER IN VERTICAL FORCED CONVECTIVE BOILING OF BINARY MIXTURES
XIII UIT National Heat Transfer Conference - Bologna, June 22÷23, 1995

EXPERIMENTAL EVALUATION OF THE ONSET OF SUBCOOLED FLOW BOILING AT HIGH LIQUID VELOCITY AND SUBCOOLING
XIII UIT National Heat Transfer Conference - Bologna, June 22÷23, 1995
International Journal Heat Mass Transfer - Vol. 40-n. 12 - pp.2879÷2885, 1997

A THEORETICAL MODEL FOR THE EVALUATION OF DIRECT CONTACT BOILING OF R 114 JETS IN WATER
Revue Générale de Thermique - Vol. 34 - n. 403-404 - pp.417÷425 - July-August 1995

PRELIMINARY REMARKS ON VISUALIZATION OF HIGH HEAT FLUX BURNOUT IN SUBCOOLED WATER FLOW BOILING
International Symposium on Two- Phase Flow Modelling and Experimentation, Rome, Oct. 9÷11, 1995

HIGH HEAT FLUX BURNOUT IN SUBCOOLED FLOW BOLING
Journal of Thermal Science - Vol. 4 - N. 3, 1995

THE EFFECT OF THE TUBE DIAMETER ON THE CRITICAL HEAT FLUX IN SUBCOOLED FLOW BOILING - TECHNICAL NOTE
International Journal Heat Mass Transfer - Vol. 39 - No. 8, pp. 1755-1757, 1996

ENERGY AND DEVELOPMENT
50th Anniversary of the United Nations and the Italian Contribution toward the realization of the “Earth Charter” - Rome, May 6÷7, 1996

THERMAL HYDRAULIC CHARACTERIZATION OF STAINLESS STEEL WICKS FOR HEAT PIPE APPLICATIONS
2nd European Thermal Sciences and 14th UIT National Heat Transfer Conference - Rome, May 29-31, 1996
Revue Gén. de Thermique - 37 - pag. 5÷16, 1998

GEOMETRICAL EFFECTS ON THE SUBCOOLED FLOW BOILING CRITICAL HEAT FLUX
European Two Phase Flow Group Meeting - Grenoble, June 2÷5, 1996

A MECHANISTIC MODEL FOR THE PREDICTION OF WATER-SUBCOOLED-FLOW-BOILING CRITICAL HEAT FLUX AT HIGH LIQUID VELOCITY AND SUBCOOLING
Fusion Technology - Vol. 29 - July 1996, pp. 499÷511

REDUCTION OF BOILING INCIPIENCE HYSTERESIS OF HIGHLY-WETTING FLUIDS USING FREQUENCY MODULATION OF PRESSURE WAVE PERTURBATIONS
15th UIT National Heat Transfer Conference - Torino, June 19÷20, 1997

HEAT TRANSFER ENHANCEMENT BY AIR INJECTION  IN FORCED AND MIXED CONVECTIVE FLOW OF WATER
15th UIT National Heat Transfer Conference - Torino, June 19÷20, 1997

VERTICAL FORCED CONVECTIVE BOILING OF REFRIGERANT BINARY MIXTURES
Revue Générale de Thermique - Vol. 36 - pp. 253÷263, 1997

GEOMETRICAL EFFECTS ON THE SUBCOOLED FLOW BOILING CRITICAL HEAT FLUX
Revue Générale de Thermique  Vol. 36, PP. 807÷814, 1997

HIGH HEAT FLUX BURNOUT IN SUBCOOLED FLOW BOILING: EXPERIMENTATION AND MODELLING
Rendiconti della Accademia Nazionale delle Scienze detta dei XL - Serie V - Vol.XXI-Parte II, Tomo I, 1997

MARS 600 MWth NUCLEAR POWER PLANT -
University of Rome “La Sapienza” - Dept. of Nuclear Engineering and Energy Conversion, 1997

DESIGN PRINCIPLES, TARGETS AND CRITERIA FOR A MULTIPURPOSE ADVANCED REACTOR INHERENTLY SAFE (MARS)
The 5th International Conference on Nuclear Engineering Proceedings of ICONE 5 - Nice, France, May 26-30, 1997
Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics Design and Safety - I.C.T.P., Trieste, March 23, 1998

TOWARDS MODULAR, INHERENTLY SAFE, PASSIVE REACTORS- The Evolution of MARS Design
Forum on Energy Security in the Third Millenium: Scientific and Technological Issues - Villa Olmo, Como, May 14÷16, 1998

HEAT TRANSFER ENHANCEMENT BY AIR INJECTION IN UPWARD HEATED MIXED CONVECTION FLOW OF WATER
1st European-Japanese Two-Phase Flow Group Meeting
36th European Two-Phase Flow Group Meeting, PORTOROZ, June 1-5, 1998

A NEW MECHANISTIC MODEL FOR THE PREDICTION OF THE CHF IN WATER SUBCOOLED FLOW BOILING
Third International Conference on Multiphase Flow - ICMF’98 - Lyon, France, June 8-12, 1998

HEAT EXCHANGERS FOR INHERENTLY SAFE REACTORS
International Conference for Sustainable Development - Instituto Superior Tecnico - Lisbon, June 13÷17, 1998

THE USE OF NEW REFRIGERANTS IN COMPACT HEAT EXCHANGERS FOR THE REFRIGERATION INDUSTRY
International Conference for Sustainable Development - Instituto Superior Tecnico - Lisbon, June 13÷17, 1998

PREDICTION OF THE CHF IN WATER SUBCOOLED FLOW BOILING USING A NEW MECHANISTIC APPROACH
16th UIT National Heat Transfer Conference - Siena, June 18÷19, 1998

HEAT TRANSFER IN UPWARD MIXED CONVECTIVE FLOW OF WATER IN A VERTICAL CHANNEL
11th International Heat Transfer Conference -Kyongiu, 23-28 August 1998

PHYSICAL INSIGHT IN THE BURNOUT REGION OF WATER-SUBCOOLED FLOW BOILING
Revue Générale de Thermique, pp. 450÷458, n. 37, 1998

UPFLOW TURBULENT MIXED CONVECTION HEAT TRANSFER IN VERTICAL PIPES
International Journal of Heat and Mass Transfer - 41(1998) pp 4037÷4054

TRANSIENT BEHAVIOUR OF A HEAT PIPE WITH EXTRACAPILLARY CIRCULATION
ENEA Technical  Report - ERG/ING 98037 - Dec. 1998
Tsinghua Science and Technology - ISSN 1007-0214 - 04/17 - pp135-145
 Vol. 7-No.2 - April, 2002

SUSTAINABLE ENERGY DEVELOPMENT
Renewable and Sustainable Energy Reviews - pp. 235÷286, 2 - 1998

PREDICTION OF THE CRITICAL HEAT FLUX IN WATER SUBCOOLED FLOW BOILING USING A NEW MECHANISTIC APPROACH
International Journal of Heat and Mass Transfer 42, p. 1457÷1466, 1999

EXPERIMENTAL STUDY OF IN-TUBE STEAM CONDENSATION IN PRESENCE OF HIGH PERCENTAGE OF NONCONDENSABLES, AIMED AT THE DESIGN OF AN INHERENTLY SAFE HEAT TRANSFER EMERGENCY SYSTEM
International Symposium on Two-Phase Flow Modelling and Experimentation - Pisa, May 23-25, 1999

ECONOMIC COMPETITIVENESS IN ELECTRIC PRODUCTION THROUGH NUCLEAR ENERGY: NEW PERSPECTIVES CREATED BY A PLANT SIMPLIFICATION
Conference Global 99 .-  Jacksonm Wyoming - August 28 - Sept. 3, 1999

ALTERNATIVE REFRIGERANT PERFORMANCE IN PLATE HEAT CONDENSERS FOR AIR CONDITIONING
International Conference on Compact Heat Exchangers and Enhancement Tecnology for the Process Industries
Banf, Alberta, CANADA - July, 18÷23, 1999
Heat and Technology - Vol. 17, n.2, 1999

DIRECT CONTACT BOILING OF INITIALLY SUBCOOLED R 114 INTO WATER
Heat and Technology, Vol. 17, n. 1, pp. 75÷84, 1999

HEAT TRANSFER ENHANCEMENT BY AIR INJECTION IN UPWARD HEATED MIXED-CONVECTION FLOW OF WATER
International Journal of Multiphase Flow - 25 - pp. 1033-1052-1999

SAFETY IN NUCLEAR PLANTS AND WASTE DISPOSAL
International Conference on Energy and Environment - Nuclear and Renewable Energies - Accademia Nazionale dei Lincei, Rome, March 8-9, 2000

THE CONCEPT OF SUSTAINABLE ENERGY DEVELOPMENT
Thermal Engineering - Vol. 47, N. 3, pp. 266-274 -  2000 -

EXPERIMENTAL STUDY OF THERMAL CRISIS IN CONNECTION WITH TOKAMAK REACTOR HIGH HEAT FLUX COMPONENTS
CP513 Nuclear and Condensed Matter Physics, edited by A. Messina
2000 American Institute of Physics 1 - 56396-929-7/00

A PHOTOGRAPHIC STUDY OF THE SUBCOOLED FLOW BOILING BURNOUT AT HIGH HEAT FLUX AND VELOCITY
Boiling 2000 - Phenomena & Emerging Applications - Anchorage, Alaska - April 30-May 5, 2000

BURNOUT IN SUBCOOLED FLOW BOILING OF WATER: A VISUAL EXPERIMENTAL STUDY
Int. Journal Thermal Science (2000) - 39 - pp. 896÷908

R22 REPLACEMENT ASPECTS IN COMPACT HEAT EXCHANGERS FOR AIR CONDITIONING
International Journal of Heat Exchangers - 1524-5608 - Vol. 1(2000), PP. 77-92

COMPARING LONG TERM ENERGY SCENARIOS
Il futuro energetico a livello mondiale – AET - Bellinzona, Nov. 28, 2000

EXPERIMENTAL INVESTIGATION OF HYDRAULIC AND SINGLE PHASE HEAT TRANSFER IN 0.130 mm CAPILLARY TUBE
XIX UIT National Congress - Modena, June 26-27, 2001
Microscale Therm. 2002ophysical Engineering, 6:85-97. 2002

TERMINAL BUBBLE RISING VELOCITY IN ONE-COMPONENT SYSTEMS
39th European Two-Phase Group Meeting - Aveiro, Portugal, 19-20 June, 2001

BUBBLE RISING VELOCITY IN SATURATED LIQUID UP TO THE CRITICAL PRESSURE
Fifth World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics
Thessaloniki, Greece, Sept. 24-28, 2001

EXPERIENCES AND TECHNIQUES IN THE DECOMMISSIONING OF OLD NUCEAR POWER PLANTS
Marconi Lecture, The Royal Swedish Academy of Sciences - Stockholm, Oct. 24th, 2001.-

DISTANCE LEARNING IN NUCLEAR ENGINEERING EDUCATION
Post Fisa 2001 Workshops - Luxembourg, Nov. 15, 2001

ON THE WAKE EFFECT IN BUBBLE RISING VELOCITY FOR ONE – COMPONENT SYSTEMS
12th International Heat Transfer Conference – Grenoble, Aug- 18—23, 2002

VISUAL INVESTIGATION OF BOILING CRISIS IN SUBCOOLED FLOW BOILING
The Arabian Journal for Science and Engineering, Vol. 27 – No. 2C – Dec. 2002

THERMAL HYDRAULIC CHARACTERIZATION OF A HEAT PIPE WITH EXTRAPILLARY CIRCULATION
International Journal of Thermal Sciences . 41 (2002) 115-123

REWETTING  OF  HOT  SURFACES  BY  DROPLET  IMPINGEMENT
40th European  Two Phase  Flow  Group  Meeting – Stockholm. 11-14  June, 2002
3rd European Japanese TwoPhase Flow Group Meeting – Certosa di Pontignano, 21-27 September, 2003

WATER SINGLE-PHASE FLUID FLOW AND HEAT TRANSFER IN CAPILLARY TUBES
Thermal Science & Engineering - Vol. 11 - No. 6 - 2003

THE SAFETY OF NUCLEAR POWER PLANTS
Joint Autumnal Conference on Large Constructions versus Safety
Accademia Nazionale delle Science detta dei Quaranta .- Academia Scientiarum et Artium Europaea  - Rome, Oct. 30, 2003

THE WAKE EFFECT  ON THE RISING VELOCITY OF SMALL BUBBLES
3rd European-Japanese Two-Phase Flow Group Meeting
Certosa di Pontignano -  21-27 September, 2003

PRINCIPLES OF NUCLEAR SAFETY: SPENT FUEL MANAGEMENT
International Centre for Theoretical Physics – Trieste, Marzo 2004

MARS, 600 MWt NUCLEAR POWER PLANT
Americas Nuclear Energy Symposium (ANES) 2004 - MIAMI - Oct- 3-6, 2004

THE WAKE EFFECT ON BUBLE RISING VELOCITY IN ONE-COMPONENT SYSTEMS
International Journal of Multiphase Flow  30 – 2004 . pp. 939-961

SAFETY IN NEW GENERATION NUCLEAR POWER PLANTS: THE MARS REACTOR
International Conference on Structural Safety and Reliability (ICOSSAR 'O5) - Rome, June 19-22, 2005

MAUS-1,5 NUCLER REACTOR FOR SPACE ELECTRIC POWER
12th Int, Conference on Emerging Nuclear Energy Systems (ICENES 2005)
Brussels, Belgium, August,  21-26 2005

NUCLEAR REACTOR FOR ELECTRIC POWER GENERATION IN SPACE APPLICATIONS
Space Nuclear Conference, 2005- San Diego, CA., June 5-9, 2005 . Paper 1133

EXPERIMENTAL STUDY ON COMPRESSIBILITY EFFECTS IN MICROTUBES
ECI International Conference on Heat Transfer and Fluid Flow in Microscale
Castelvecchio Pascoli, September 25-30, 2005

MICROTUBE HEAT TRANSFER SCALING EFFECTS - AN
EXPERIMENTAL VALIDATION
ECI International Conference on Heat Transfer and Fluid Flow in Microscale
Il Ciocco, Castelvecchio Pascoli, September 25-30, 2005

CHARACTERIZATION OF FLUID DYNAMIC BEHAVIOUR AND CHANNEL WALL EFFECTS IN MICROTUBE
International Journal of Heat and Fluid Flow 27 (2006) 135-143

MICROTUBE LIQUID SINGLE-PHASE HEAT TRANSFER IN LAMINAR FLOW
International Journal of Heat and Mass Transfer - 49 (2006) 3538-3546

FLUID FLOW AND HEAT  TRANSFER FOR MICROTECHNOLOGIES
Rendiconti Accademia Nazionale delle Scienze, detta dei XL – Memorie di Scienze Fisiche e Naturali – 123° 2005 – Vol. XXIX– t. 1, pp.67-89

SAFETY IN NUCLEAR POWER: A PROPOSAL
Advances in New and Sustainable Energy Conversion and Storage Technologies
Dubrovnik September, 23-25, 2006

EFFECT OF GAS INJECTION MODE AND PURITY OF LIQUID ON BUBBLE RISING IN TWO COMPONENT SYSTEMS
Experimental Thermal and Fluid Science 31 (2006) 37-53
NUCLEAR ENERGY IN THE WORLD
3rd Conference on the Future of Science – Fondazione Giorgio Veronesi – Venezia, Fondazione Fini -  Sept. 19-22, 2007

Note

VOLUMI
(come autore)


ASPETTI FONDAMENTALI DELL'EBOLLIZIONE

Edizioni CNEN - Serie Trattati - 1968

NOTE DI SCAMBIO TERMICO

Edizioni CNEN - Serie Ingegneria - 1968

ELEMENTI DI TERMOTECNICA DEL REATTORE - Serie Trattati - 1969


TERMOTECNICA SPERIMENTALE

Edizioni ENEA - Serie Trattati ¬ 1982

IMPIANTI NUCLEARI

Edizioni UTET - Torino  - 1a   edizione 1976 - 2a   edizione1986

THERMAL HYDRAULICS - Vol. I - II

CRC Press - Inc. 1988

INGEGNERIA DEI REATTORI NUCLEARI A FUSIONE

Edizioni ENEA - Serie Trattati 1991


NUCLEAR PLANTS DECOMMISSIONING
Technology, cost evaluation, management, regulation, safety, health and environment protection
M. Cumo, I. Tripputi, U. Spezia
Università di Roma “La Sapienza” – Scuola di Specializzazione in Sicurezza e Protezione  - Giugno 2002


IMPIANTI E INSTALLAZIONI INDUSTRIALI AD ALTO RISCHIO
M. Cumo, M. Frullini
Università di Roma “La Sapienza” – Scuola di Specializzazione in Sicurezza e Protezione  - Maggio 2003

SAFETY IN NUCLEAR POWER: A PROPOSAL
Sustainable Energy Technologies . Editors K. Hanjalic, R. van de Krol, A. Lekic
Springer, ISBN 978-1-4020-6723-5 - 2007

LWR SAFETY AND RISK ASSESSMENT FROM GEN. II TO GEN. IV - Course VI -
CEA INSTN 2007 – International School in Nuclear Engineering – Saclay, Francia, Sett. 2007

FISSIONE NUCLEARE E APPLICAZIONI
Enciclopedia della Scienza e della Tecnica, Treccani, Vol. V – Febbraio 2008

STATO DELLE NUOVE INIZIATIVE IN EUROPA CON REATTORI DI GENERAZIONE III+
L’OPZIONE NUCLEARE IN ITALIA: QUALI PROSPETTIVE?
Collana Quaderni AIEE – Milano, 7 Ottobre 2008
 

REACTOR DISMANTLING AND WASTE MANAGEMENT – Course VIII
CEA INSTN 2008 – International School in Nuclear Engineering – Saclay, Francia, Ott. 2008

Volume Impianti Nucleari presso l’editrice Sapienza (2008) (nuova edizione del testo UTET del 1987, aggiornata con i progressi dell’ultimo ventennio)

 
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