ALAIN JEAN PAUL MAILLIAT Dr,

After having received from Marseille University a PhD of Mathematics in 1974 and a Doctorat es Sciences in Physics in 1980, he joined the Commissariat à l’Energie Atomique in 1981. There, he started his career as an analyst of the PHEBUS LOCA program, Then he was responsible for the development of the first version of the ICARE code devoted to Severe Accident phenomenology. Next, he was responsible for the definition and the dimensioning of the PHEBUS FP experimental circuits and the analyses of the first tests of this program. To day, he belongs to the management staff of the Department for Prevention of Major Accidents (DPAM) of IRSN where he is in charge of the definition of the future in pile research programs He is a specialist of Light Water Reactor researches devoted to nuclear safety questions. His expertise are related both with Design Basis Accidents, (LOCA) and Severe Accidents issues . Regarding LOCA, his skills are thermo hydraulics, high burnup fuel rod behavior and quenching. In the domain of Severe Accidents, his expertise concerns core degradation, fission products emission, aerosol transport, iodine radiochemistry and source term. He contributed in the 3rd, 4th and 5th CEE programs. He initiated the European Severe Accident PIRT procedure EURSAFE. In 2000, he was one of the few non US experts who contributed to the US NRC PIRT Panel on LOCA issues. In 2002, he was invited to contribute to the international panel for the evaluation of the Spanish Fission researches programs. In addition to his Reactor Safety Activities, since 1990, Alain Mailliat is also Lecturer at the Marseille University and promotes aerosols physics teaching in the south of France . In 2001 he was awarded by the Ministry of Education for services to education. ALAIN MAILLIAT LIST OF OPEN PUBLICATIONS

EUROPEAN EXPERT NETWORK FOR THE REDUCTION OF UNCERTAINTIES IN SEVERE ACCIDENT SAFETY ISSUES (EURSAFE) Journal of Nuclear Engineering and Design 232(2005) 309-346, ELSEVIER PROPOSAL FOR A FUTURE PHEBUS TEST ON AIR INGRESS 30 Reunion Anual Sociedad Nuclear Espanola, 29 septi-1 de Octu 2004, Alicante, Espagna ETUDE PHÉNOMÉNOLOGIQUE DU DÉPÔT SEC D’AÉROSOLS SUR UN COUVERT VÉGÉTAL ASFERA, 19eme congrès français sur les aérosols,10-11 décembre 2003, Paris, Institut National Agronomique RESEARCH NEEDS TO RESOLVE PENDING LOCA ISSUES, Colloquium on High Burnup Fuels for LWRs. January 23,2003 Massachusetts Institute of Technology, Cambridge, MA SEPARATE EFFECTS AND IN-PILE SAFETY PROGRAMMES :CURRENT STATUS AND FUTURE EXPERIMENTAL NEEDS, Future European Needs in Materials Research Reactors, 27 février-1 Mars 2003 Cadarache. THE PHEBUS FISSION PRODUCTS PROGRAMME,

EUROCOURSE 2003 CORIUM : Severe Accident R&D and Nuclear Power Plant Safety, Janvier 2731,2003, Aix en Provence EURSAFE PROJECT : THE EUROPEAN SEVERE ACCIDENT PIRTS, CSARP Meeting, May 5-7, 2003-12-15 Bethesda, Maryland, USA IRSN PLANS FOR FUTURE EXPERIMENTAL PROGRAMMES, 5th Technical Seminar on the PHEBUS FP PROGRAMME, Centre des Congrès, Aix en Provence, june 24-26, 2003 EUROPEAN NETWORK FOR THE REDUCTION OF UNCERTAINTIES IN SEVERE ACCIDENT SAFETY ISSUES (EURSAFE), FISA 2003, Luxembourg, Novembre 10-13, 2003 ETUDE PHENOMENOLOGIQUE DU DEPOT SEC D’AEROSOLS SUR UN COUVERT VEGETAL, ASFERA 2003 : 18ème Congrès Français sur les Aérosols,, 10 et 11 décembre 2003,l'Institut National Agronomique à Paris (INA), 75231 Paris Cedex 05 IRSN SOURCE TERM LOCA PROGRAM LOCA PART, OECD expert Group on PHEBUS-LOCA Project, 19-20 November 2003-12-15 Madrid, Spain EURSAFE PROJECT : STATUS OF THE EUROPEAN SEVERE ACCIDENT PIRTS, EUROSAFE 2002, Berlin, 4&5 Novembre 2002, Allemagne THE IRSN FUTURE PROGRAMMES, OECD-SEG Fuel Safety Margins Meeting, Aix en Provence 13-15 May 2002, France. PRESENTATION OF THE PHEBUS-2K PROGRAM . CSARP Meeting, Albuquerque, May 6-8, 2002, New Mexico, USA FUTURE PROGRAMMES IN THE PHEBUS FACILITY. Committee for Reactor Safeguards, Washington DC, May 3, 2002, USA USE OF EUROPEAN RESEARCH REACTORS FOR SAFETY EXPERIMENTS, CURRENT REQUIREMENTS AND FUTURE NEEDS, FEUNMARR PROJECT Meeting, March 27-28, 2002, Aix en Provence, France IRSN FUTURE PROGRAMMES IN THE PHEBUS FACILITY, Fuel Safety Research Specialist’s Meeting, TokaÏ-Mura, March 4-5, 2002, Japan AN IPSN RESEARCH PROGRAMMES TO RESOLVE PENDINGT LOCA ISSUES EUROSAFE Conf., Paris, 5-6 Nov 2001, France NEEDS FOR EXPERIMENTAL PROGRAMMES ON LOCA ISSUES USING HIGH BURNUP AND MOX FUELS Nuclear Safety Research Conf., 22-24 Oct 2001, Washington DC,USA IPSN PROPOSAL FOR HIGH BURNUP FUEL LOCA EXPERIMENTAL PROGRAMS AIEA Conf. LOCA Tech. Workshop Group. Halden, 10-13 September 2001, Norway IPSN ANALYSIS OF EXPERIMENTAL NEEDS FOR SOLVING LOCA PENDING ISSUES OECD LOCA Topical Meeting, Aix en Provence, 22-23 Mars 2001 THE PHEBUS-2K PROJECT ON SEVERE ACCIDENTS, EUROSAFE, KÖLN, 6-7 Nov 2000

IPSN PHEBUS-2K PROGRAMME OVERVIEW, CSARP 2000, May 8-12,2000, Bethesda, MA, USA PHEBUS –2000 PROGRAMME, 4th Seminar on the PHEBUS FP Programme, March 20-22,2000 Marseille, France LE TERME SOURCE : LE CONFINEMENT DES PRODUITS DE FISSION. La Revue Générale Nucléaire 1977 N°1 Janvier-Février. ESCADRE CODE DEVELOPMENT AND VALIDATION - AN OVERVIEW, SARM’97. Severe Acc. Risk and Management Conf. PIESTANY, SLOVAQUIE, 16-18 juin 1997 SOME IMPORTANT OPEN ISSUES FOR SOURCE TERM ESTIMATES IN SEVERE ACCIDENT SEQUENCES, SARJ 96 208-30 Oct 96, Tokyo, Japan ESCADRE MOD0 AND SAFETY OF LWRS,

RALOC MOD2 ASSESSMENTS: MAJOR FINDINGS AND RELEVANCE TO THE

Int Seminar on Heat and Mass Transf in Severe Reactor Accidents, May 22-26, 1995, CESME, IZMIR, TURKEY AÉROSOLS ET SÛRETÉ NUCLÉAIRE : APERÇU DES MÉTHODES ET DES PROGRAMMES DE L’IPSN, Les Etudes et Recherches en Sûreté Nucléaires et Préventions des Risques Majeurs en Région PACA, 18/05/95, Marseille, Hôtel de la Région. CONTAINMENT PHENOMENA, Third Reinforced Action on Reactor Safety, FISA-95 Symposium, Luxembourg, 20-22 November, 1995 Nuclear Science and Technology : Source Term Code Assessment, European Commission, Report EUR-16509-EN, 1995 PHEBUS FP AND CABRI PWR SAFETY RESEARCH PROGRAMMES, 9th KAIF/KNS/UKAEA Annual Conf., SEOUL, 04-06 Apr. 1994, KOREA JERICHO CODE ASSESSMENT AND DEVELOPMENT ON THE CONTAINMENT TEST PROGRAMME.

PHEBUS THERMAL-HYDRAULICS

Int. Conf. on New trends in Nuclear System Thermal-Hydraulics, PISA, MAY 30th, June 2d, 1994, (ITALY) ANALYSIS OF THE PHEBUS FPT0 CONTAINMENT THERMALHYDRAULICS WITH JERICHO AND TRIOVF CODES. Third Int. Conf. on Containment Design and Operation. TORONTO, 19-21 Oct.1994, CANADA ESCADRE MOD0 AND ITS VALIDATION; CSARP Meeting, May 3-7 1993, Maryland, USA COMPARISON OF THE SOPHAEROS, TRAPF AND AEROSOLS-B2 CODES WITH THE AEROSOL TRANSPORT EXPERIMENT LA3B OF THE LACE PROGRAMME. 12th Annual Conf of Am. Ass. For Aerosol research. 0AK BROOK, 11-15 Oct 1993, Illinois(USA)

THE CALCULATION PROGRAMME TO PREPARE THE FIRST PHEBUS FP TEST, Twentieth Water Reactor Safety Information Meeting, BETHESDA(MD), October 21-23, 1992 (USA) CALCULATIONS OF THE PHEBUS FP EXPERIMENTS ,

Workshop on Severe Accident Researches, TOKYO, November 1992, (JAPAN) OVERVIEW OF THE PHEBUS FP PROGRAMME, Sixth Korean Atomic Industrial Forum, Korean Nuclear Society, SEOUL, April 15-17, 1991,(KOREA) OVERVIEW OF THE PHEBUS FP PROGRAMME AND IN CORE ASPECTS OF THE FIRST TEST, CSARP Meeting BETHESDA(MD), May 6-10, 1991,(USA) PHEBUS FPT0 TEST PRECALCULATIONS, seminar of the PHEBUS FP project, CADARACHE, June 5-7, 1991,(FRANCE) FIRST PHEBUS FP TEST : OBJECTIVES AND PRECALCULATIONS, American Nuclear Society, International Topical Meeting, PORTLAND (ORG), Jul 2225,1991,(USA) ESCADRE SYSTEM ASSESSMENT, Escadre VVER meeting, Budapest, Sept 22-25, 1991,(HONGARY) OVERVIEW OF THE PHEBUS FP EXPERIMENTAL PROGRAMME", XVI Annual Meeting of the Spanish Nuclear Society, OVIEDO, Oct 14-26, 1990,(SPAIN) OVERVIEW OF THE PHEBUS FP PROGRAMME, Severe Accident conference, TOKAI MURA, Nov 21-22, 1990,(JAPAN) REPRESENTATION OF THE FISSION PRODUCTS BEHAVIOUR DURING SEVERE ACCIDENTS INTO A GLOBAL EXPERIMENT", Int. Sem. on Fission Product Transport Processes in React. Accidents, DUBROVNIK, May 22-26, 1989,(YU) ANALYTICAL ASSESSMENT OF THE CAPABILITY OF A SCALED DOWN IN PILE TEST FACILITY TO SIMULATE PWR PHENOMENA UNDER SEVERE ACCIDENT CONDITIONS". American Association for Aerosol Research, Eighth annual meeting, RENO, NEVADA, Oct 10-13, 1989,(USA) SCOPING CALCULATIONS IN SUPPORT OF THE PHEBUS FP EXPERIMENTAL PROGRAMME", Seminar of the commission contribution to Reactor Safety Research, VARESE, Nov 20-24, 1989,(ITALY) ICARE : A COMPUTER CODE FOR SEVERE FUEL DAMAGE ANALYSIS", Int. ENS/ANS conf. on thermal reactor safety, AVIGNON, Oct 2-7, 1988,(FRANCE) ÉTUDE DE L'EFFET D'UN APPORT DE CHALEUR SUR UN ÉCOULEMENT DIPHASÉ. Thèse de Doctorat de spécialité, Novembre 1974, UER de Mathématiques, Université de Provence SUR LA DIFFUSION TURBULENTE D'UNE GRANDEUR SCALAIRE PASSIVE. Compte-Rendu Acad. Sc. Paris, t 290(10 mars 1980) CONTRIBUTION À L'ÉTUDE DES MÉCANISMES DE LA DIFFUSION TURBULENTE ET DE QUESTIONS CONNEXES. Thèse de Doctorat Es-Sciences, Université de Provence, 22 décembre 1980 SUR LES PROPRIÉTÉS DES DENSITÉS DE PROBABILITÉ LAGRANGIENNES. Compte-Rendu Acad. Sc. Paris, t 292(4 mai 1981)