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GN
Gregory Nicaise
95
Documents
Présentation
Gregory ORTEGA NICAISE is a mathematical physicist and chemist, expert in nuclear reactor accident modelling and fission products physics and chemistry.
He is specialised in condensed matter complex systems at molecular, atomic and electronic scales, with equilibrium and non-equilibrium thermodynamics formalisms. He namely discovered the non-diffusional liquid lead/lead-bismuth embrittlement phenomenon of nuclear grade steels during his doctoral studies.
He has over 20 years experience in science-based nuclear safety expertise at IRSN where he led and contributed to experimental and computational research in nuclear reactor core melting accidents and radiological source term evaluation. Namely he developed mesoscale mechanistic models of fission product behaviour in irradiated nuclear fuels up to melting temperature, iodine radiochemistry models under severe accident conditions, theories on metastable oxidation solidification of melted nuclear fuel under steam explosion conditions, and thermomechanical analysis of power reactor lower head vessel in contact with relocated corium using full-coupled numerical modelling techniques. Beyond his research activities, he also reviewed severe accident mitigation and safety options of main GEN IV reactor concepts and safety options of nuclear waste deep geological disposals.
Nowadays, he is heading the nuclear accident computational division at IRSN’s Emergency Technical Centre where he leads the development of fast computational tools for nuclear emergency national preparedness and response, being also emergency responder. His technical expertise is regularly requested at international level (AIEA, ETSON, WENRA…).
Domaines de recherche
Chimie théorique et/ou physique
Physique mathématique [math-ph]
Physique Nucléaire Théorique [nucl-th]
Compétences
Nuclear reactor safety scientific expertise
Nuclear reactor accident modelling
Nuclear emergency preparedness and response
Irradiated nuclear fuel mesoscopic modelling
Thermochemistry of nuclear fuels up to melting temperature
Fracture mechanics
Statistical thermodynamics
High performance computing and simulation
Publications
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Accident Scenario Database at IRSN’s Technical Emergency CentreIAEA conference on the developement of preparedness for national and international emergency response, IAEA, May 2021, Vienna (AUSTRIA), Austria
Communication dans un congrès
irsn-04296078v1
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Radiological characterization of in-pile irradiated graphite - Metrological problem, mathematical method and physical modelisationTechnical meeting on the International Project on Irradiated Graphite Processing Approahces (GRAPA), International Atomic Energy Agency, Jun 2017, Vienna (AUSTRIA), Austria
Communication dans un congrès
hal-04258507v1
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A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scaleEUROSAFE FORUM 2015, European Technical Safety Organisations Network, Nov 2015, Brussels (Belgium), Belgium
Communication dans un congrès
hal-04258535v1
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Characterisation of PWR vessel steel tearing under severe accident condition temperatures21st International Conférence on Structural Mechanics in Reactor Technology, SMIRT 21, Nov 2011, New Delhi, Inde, India
Communication dans un congrès
irsn-04295239v1
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Finite element modelling of unstable crack propagation of nuclear steel at high temperature with cohesive elements9e Colloque national en calcul des structures, CSMA, May 2009, Giens, France
Communication dans un congrès
hal-01412110v1
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Structure defects evolution in irradiated UO2 nuclear fuels modeled with MFPR codeInternational Meeting on LWR Fuel Performance, Sep 2004, Orlando (Florida), United States
Communication dans un congrès
irsn-04295119v1
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Analysis of accidental sequence tests and interpretation of fission product release: interdependence of Cs, Mo, and Ba release11th Symposium on Thermodynamics of Nuclear Materials, Sep 2004, Karlsruhe, Germany
Communication dans un congrès
irsn-04294828v1
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VERCORS program: results and interpretationFuel Safety Research Meeting- JAEA, JAEA, Mar 2004, Tokyo (JP), Japan
Communication dans un congrès
irsn-04295137v1
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Fission products interdependance on the release process from irradiated nuclear fuels up to melting temperature8th International Conférence on CANDU Fuel, Sep 2003, Honey Harbour, Canada
Communication dans un congrès
irsn-04295081v1
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Fission gas release from irradiated UO2 fuel : Development of new mechanistic code MFPR and applications8th International Conférence on CANDU Fuel, Sep 2003, Honey Harbour, Canada
Communication dans un congrès
irsn-04295148v1
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Development of mechanistic code MFPR for modeling fission product release from irradiated UO2 fuel. Part2: Application to integral tests VERCORS 4/5 and PHEBUS FPT0/1Internat. Conference “TopFuel 2003: Nuclear Fuel for Today and Tomorrow. Experience and Outlook", Mar 2003, Wurzburg, Germany
Communication dans un congrès
hal-04441096v1
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Risk of liquid metal embrittlementMEGAPIE Technical Workshop, Feb 2001, Karslruhe, Germany
Communication dans un congrès
hal-04441060v1
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Embrittlement of a martensitic by liquid leadTechnologies, Materials, Thermal-Hydraulics for Lead Alloys (TECLA) Meeting, Mar 2001, Cadarache, France
Communication dans un congrès
hal-04441069v1
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Embrittlement of a martensitic steel by liquid leadEuropean Conference for PhD students in Physical Sciences, European Physical Society, Jun 2000, Lausanne, Switzerland
Communication dans un congrès
hal-04441012v1
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Embrittlement of a martensitic steel by liquid leadWorkshop on grain boundary wetting by liquid metals, Jan 2000, Grenoble, France
Communication dans un congrès
hal-04441020v1
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Embrittlement of the martensitic steel 91 by liquid leadInternational Workshop on Spallation Materials, Oct 2000, Vienna, Austria
Communication dans un congrès
hal-04441037v1
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Embrittlement of a martensitic steel by liquid leadEuromat Junior 2000, Aug 2000, Lausane, Switzerland
Communication dans un congrès
hal-04441032v1
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Embrittlement of a martensitic by liquid leadTechnologies, Materials, Thermal-Hydraulics for Lead Alloys (TECLA) Meeting, Oct 2000, Karslruhe, Germany
Communication dans un congrès
hal-04441056v1
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Sensibilité d'un acier martensitique à la fragilisation par les métaux liquidesMécanique [physics.med-ph]. Université des Sciences et Technologie de Lille - Lille I, 2001. Français. ⟨NNT : ⟩
Thèse
tel-00454185v1
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