www.instn.cea.fr/en/

www.cea.fr/english

17th EDITION
INTERNATIONAL SCHOOLIN NUCLEAR
ENGINEERING

2023
In France

Internationally known
expert lecturers
mostly from the CEA,
the leading researchorganisation in France
for nuclear energy

SACLAYMARCOULECADARACHE

6 Doctoral-level Courses
in Nuclear Engineering
From January 16 to March 10, 2023
For each course, technical visitsof CEA facilities are plannedwww.enen.eu

www.instn.cea.fr/en/

www.cea.fr/english

INTERNATIONAL SCHOOLIN NUCLEAR ENGINEERING

2023
In France

17thEDITIONSACLAYMARCOULECADARACHEInternationally known expert lecturers
mostly from the CEA, the leading researchorganisation in France for nuclear energy

6 Doctoral-level Courses
in Nuclear Engineering
From January 16
to March 10, 2023

www.enen.eu

For each course,
technical visitsof CEA facilities
are planned

I N T E R N AT I O N A L S C H O O L I N N U C L E A R E N G I N E E R I N G

GFR, experimental
reactor Allegro

Pin-type fuel elementof Gas Fast-cooled
Reactor (GFR)

Neutronics calculation ofEPR core with APOLLO3
Large scale bubble
simulationActinide complex solvatedby extraction molecule

ABOUT THE SCHOOLINSTN, the French school for energy and health technology is organizing theInternational School in Nuclear Engineering, promoting knowledge in the field ofnuclear sciences at a high education level.
 he 2023 edition will offer 6 one-week advanced courses in nuclear engineeringT
to be held in France (Cadarache, Marcoule, or Saclay), in January and March 2023.
Participants have the possibility to choose the course they want to follow, from only
one to all six courses.
 he courses are designed for young researchers, PhD students, post-doctorates
Tand engineers, already having a Master of Science in nuclear engineering as a background. They present the international state-of-the-art in the main topics of nuclear
engineering: Reactor core physics, thermal hydraulics, materials, fuels, fuel cycleand nuclear waste.
3 ECTS will be awarded for each successfully completed course (one week).

I N T E R N AT I O N A L S C H O O L I N N U C L E A R E N G I N E E R I N G

INFORMATIONVenue

The courses will be held at INSTN locations in Saclay (P5F3+J94 Saclay, 20 km
southwest of Paris),
Cadarache (MQQ6+8C Saint-Paul-lez-Durance, 40 km from Aix-en-Provence) andMarcoule (4MRW+5R Bagnols-sur-Cèze, 30 km from Orange).

Registration deadline

December 2nd, 2022 for all courses.

Registration fees

Professionals: €2510 for the first course, €1255 for each additional course.
Students: €710 for each course.

CEA, ENEN member institutions: special rates.

Fees include lectures, documentation and lunches.

Contacts

Technical Advisor: Claude Renault - claude.renault13@orange.fr

General coordination/Info.: Stéphane WISNIEWSKI – stephane.wisniewski@cea.fr

Cadarache

Course 3 - Reactor Core Physics: Deterministic and Monte Carlo Methods
January 16 to 20, 2023
Course 4 - Nuclear Fuels for Light Water Reactors and Fast Reactors
January 23 to 27, 2023
Contact for registration: Aurélie Fuessinger - aurelie.fuessinger@cea.fr

SaclayCourse 1 - Thermal Hydraulics and Safety
January 30 to February 3, 2023
Course 2 - Materials for Nuclear Reactors, Fuels and Structures
February 6 to 10, 2023
Contact for registration: Fany Guelah - irfana.guelah@cea.fr

Marcoule

Course 5 - Nuclear Fuel Cycle: from Strategy to Processes
February 13 to 17, 2023
Course 6 - Nuclear Waste Management
March 6 to 10, 2023
Contact for registration: Laura Raibaldi - laura.raibaldi@cea.fr

I N T E R N AT I O N A L S C H O O L I N N U C L E A R E N G I N E E R I N GOUTLINE PROGRAMME OF COURSES
Course 1 - Thermal Hydraulics and Safety(D. Bestion, F. Fichot, E. Studer)Learning outcomes: give practical and relevant examples of thermal hydraulics of light water reactors(LWR) and describe modelling and multi-phase phenomenology of severe accidents in LWRs.
Main two-phase flow phenomena in LWRs
Multi-scale modelling of LWR thermal hydraulics
System code modelling of reactor thermal hydraulics, including advanced modelling LWR transient
analysis methodology with PIRT, Scaling, Code Development, Verification and Validation plus
Uncertainty Quantification
Application of the methodology to LOCA analysis
Application of one-phase and two-phase CFD to reactor thermal hydraulic issues
Multiphase phenomena and modelling of severe accidents in LWRs
Hydrogen risk (production, dispersion, combustion, mitigation)

Course 2 - Materials for Nuclear Reactors, Fuels and Structures(J-C. Brachet, E. Clouet, J. Garnier, F. Garrido, G. Gutierrez, E. Meslin, S. Pellegrino)
Learning outcomes: identify the major materials used in nuclear reactors : Steels, Zr alloys andcarbides,analysis the mechanisms of the irradiation effects on the materials, describe the evolution of the
microstructure and the impact induced by irradiation on the properties of the major materials.
 Mechanisms of irradiation damage: neutrons, photons, electrons
Behaviour of materials under irradiation: ferritic steels for reactor pressure vessel, austenitic stainlesssteels for internals or fuel cladding (FBR), Zr alloys for fuel cladding and fuel assemblies (LWR)
Zr alloys in accidental conditions and Enhanced Accident Tolerant Fuel claddings
Fuel materials (UO2, PuO2): irradiation-induced effects
Materials for high temperature conditions: SiC, ZrC, low swelling alloys
Materials for fusion: low activation materials, resistance to high-energy neutrons, breading blankets

Course 3 - Reactor Core Physics: Deterministic and Monte Carlo Methods(A. Zoia, J. Tommasi, J-F. Vidal)

Learning outcomes: identify advanced numerical methods to solve the Boltzmann equation for neutrontransport and recent deterministic and probalistic methods APPOLO2/3 and TRIPOLI4 codes.
 hain reaction and neutron balanceCNeutron slowing-down and resonance absorption, self-shielding modelling
The neutron transport equation and calculation schemes: the steady-state integro- differential transport
equation. The neutron diffusion equation… Verification and validation of neutronics code package:process, sensitivity and uncertainty studies The Monte Carlo method for solving the transport equation
Monte Carlo techniques: fixed source, variance reduction, criticality, perturbation calculations, adjoint
calculation, applications to shielding

Course 4 - Nuclear Fuels for Light Water Reactors and Fast Reactors(J. Noirot, Coordinator)

Learning outcomes: describe the design and the fabrication of the nuclear fuels as well as the fuel thermaland mechanical behavior i, reactor operation, identify the main limiting phenomena (for safety and design).
 uclear fuels fundamentals
N­Fuel element thermal performance and temperature effects Nuclear fuel behaviour under irradiation
­Main limiting phenomena in the different types of fuels­Fuel challenges for the future

I N T E R N AT I O N A L S C H O O L I N N U C L E A R E N G I N E E R I N GATALANTE
facility

Neutronics and thermal-hydraulics
Coupling for SFR simulation

The EPR

CIGEO projectCourse 5 - Nuclear Fuel Cycle: from Strategy to Processes(Ch. Sorel)

Learning outcomes: perform a critical analysis of the various waste management options and identify how
scientific studies play a part in addressing the issues related to nuclear waste management.
From uranium ore mining to spent nuclear fuelFundamentals of fuel cycle: chemistry of actinides and fission products
The current industrial process: scientific basis and process modellingTowards the 4th generation nuclear energy systems: scientific and industrial challenges associated to
the Pu-multirecycling
Minor actinide recycling as a potential option for waste management optimization

Course 6 - Nuclear Waste Management(C. Cau Dit Coumes, C. Ferry, M.Fournier, S. Gin, F.Lemont)
Learning outcomes: perform a critical analysis of the various waste management options and identify how
scientific studies play a part in addressing the issues related to nuclear waste management.
Waste management options and related issues Treatment of radioactive organic waste
Waste conditioning: concrete and vitrification
Science contribution to economic, safety and societal issues
Case study

Lecturers are experienced in teaching inseveral Masters of Science and Engineering
programmes. They also supervise PhD
students in their research activities.
Dominique Bestion, Director of Research at theCEA, has developed two-phase flow models
for the CATHARE system code for 35 years andhas strongly involved in the development of theNEPTUNE multi- scale thermal hydraulic simulation platform including two-phase CFD capabilities. He coordinated thermal hydraulic activitiesof the EUROFASTNET, NURESIM, NURISP andNURESAFE European Projects for a nuclear
reactor multi-physics and multi-scale simulation
platform. He also coordinated Working Groupsof OECD-NEA for the application of CFD tonuclear safety with Best-Practice Guidelines,
V&V and uncertainty quantification. He is professor at Ecole Polytechnique. He also teaches at
INSTN, ECP, ENSE3 and in international courses(ETH-Zurich Short Couse, IAEA training sessions, OECD THICKET Course, FJOH SummerSchools…).
Jean-Christophe Brachet is a CEA International
Expert on nuclear materials and Professor atINSTN. His expertise covers physical metallurgyof chromium-rich ferritic-martensitic steels, Zr
alloys and Enhanced Accident. Tolerant Fuelcladdings (LWR). He authored more than 60papers and participated to numerous international symposiums or workshops as lecturer or as
chairman of specific sessions. He is inventor orco-inventor of 5 patents.
Dr Céline Cau Dit Coumes is an international
expert at the CEA. She has been involved inradioactive waste management for more than
20 years and works in a laboratory devoted
to the design and characterization of cementbased materials for the conditioning of low andintermediate-level radioactive wastes. She is theauthor (or co-author) of 50 papers publishedin peer-reviewed international journals, 7 bookchapters, and 3 patents. She has been involved
in several international research projects (IAEA,Chinese Atomic Energy Agency, IFIN-HH Romania). She also performs expert evaluations onrequest of waste producers and teaches cement
chemistry at Montpellier University.
Emmanuel Clouet is Senior Expert in the Physical Metallurgy Lab of the Department for Nuclear Materials at CEA Paris-Saclay. His research
activity pertains to the multiscale materials
modeling to study plasticity in metals and alloys
and kinetic evolution of materials under irradiation, with a special emphasis on zirconium andtitanium alloys. He also is an associate editor for
Acta and Scripta Materialia journals.
Florian Fichot, international Expert on severe
accidents in nuclear reactors at Institut de Radioprotection et de Sûreté Nucléaire (IRSN). He has
been working for 25 years in the field of physicalmodelling and numerical simulation of severe
accidents in nuclear reactors, particularly in themodelling of core degradation, thermal-hydraulics and corium behaviour. Most notably, he took
part in the development of the ICARE/CATHAREand ASTEC codes. His expertise covers the twophase flow in porous media, the phase changeof multi-component mixtures and in- vesselor ex-vessel melt retention strategies for Light
Water Reactors. He was coordinator of the European project IVMR (2015-2020). He teaches in
the frame of European NUGE- NIA courses andIAEA summer schools.
Cécile Ferry is CEA Senior Expert on physico-chemistry of radioactive wastes and spent
nuclear fuel. She worked on spent nuclear fuellong-term evolution under disposal conditions
and on radionuclide migration in soils and rocks.
She coordinates CEA R&D projects on radioactive wastes characterization, conditioning, longterm behaviour and disposal.

Maxime Fournier is a Research Engineer at
the CEA and Lecturer at INSTN. His expertisecovers the chemical durability of nuclear glasses
destined to deep geological dispo- sal andconventional glasses for industrial applications,the formulation and charac- terization of glassy
materials for the confi- nement of waste fromdecommissioning and dismantling operations.
He has been involved in the coordination ofTheramin and PreDisposal RadWaste Europeanprojects. He co-authored more than 20 publications. He supervises PhD students and teaches
to Master degree students at Montpellier University, ENSCM, Aix Marseille University, Chimie
ParisTech, Grenoble Alpes University and Sorbonne University.
Jérôme Garnier is Research Engineer and expert
on nuclear materials at the CEA. He is in chargeof the material research and development
programme in support of the realization of thecore vessel and internal structures of the newJules Horowitz Materials Testing Reactor (JHR).
In 2012, he was awarded the J. Gaussens SFEN
(French Nuclear Society’s) prize, in particular for
his work on the austenitic stainless steels.
Frederico Garrido is Professor of Materials Chemistry at the Université Paris-Saclay, Orsay. He isan expert in the interaction of energetic particles
with matter and radiation damage physics, especially applied to nuclear ceramic materials usedas transmutation matrices (oxides and carbides).
He has co-authored over 100 scientific papers inpeer-reviewed journals. He became also a recipient of the Bronze Medal of the French National
Centre for Scientific Research. In addition he isco-Director of the Master Nuclear Energy, which
is run by the Paris-Saclay University.
Stéphane Gin received a PhD degree from Poitiers University, France, in 1994. Since 1995, hehas been working at the CEA Marcoule. In 2001,
he took the lead of the “Long term behaviour ofHLW glass” group. This CEA team of 25 people
focuses on fundamental and applied issues
related to the geo- logical disposal of high-level and intermediate level waste glass. From2012 to 2013, he was visiting scientist at PacificNorthwest National Laboratory, USA. Dr Gin isalso part of advisory boards on high-level waste
management in Belgium, the UK, and the USA.
He is author and co-author of about 100 papers
and wrote acclaimed books on nuclear waste
management for the general public.
Gaëlle Gutierrez is a research engineer in thePhysical Metallurgy Lab of the Department for
Nuclear Materials at the CEA Paris-Saclay. Her
research activity is focused on the radiation damage effect, especially applied to nuclear ceramic materials such as oxides (UO2, CeO2) andcarbides (B4C, SiC, Graphite). She has authoredand co-authored over 30 scientific articles inpeer-reviewed journals. She is also the operation manager of the JANNUS Saclay irradiation
platform.
Florent Lemont is Research Director at the CEA
and lecturer at INSTN. He has worked for over 25years in the field of high temperature chemistry
applied to the separation of radioelements inmolten salt media, to the combustion of solid
or liquid contaminated organic materials, tothe production of hydrogen by thermochemical cycles, to the gasification of biomass, to theoptimization of plasma technologies and to thefabrication of Mox fuels. He is author or co-author of 50 papers published in peer-reviewed
international journals and 16 patents.
Estelle Meslin, Senior expert at the CEA on nuclear materials. She has 15 years of experiencein the field of physical metallurgy of materials under irradiation, especially on Fe-based materials(Reactor Pressure Vessel steels, ferritic/martensitic steels, ODS and Eurofer steels) but also on Wor Al alloys. In 2014, she was awarded the J. Rist
medal of the SF2M (Société Française de Métallurgie et Matériaux) awarded to young scientists.
She has authored or co-authored more than 30
papers published in peer reviewed international
journals and participated to numerous international symposiums or works- hops as lecturer or

as chairman of specific sessions.
Jean Noirot is International Expert at the CEA. He
has been working for more than 20 years in thefield of nuclear fuel post-irradiation examination.
With techniques going from gamma-scanning tomicro-analyses, he has gained a wide experienceon fuel behaviour, fast breeder reactor fuel, pressurized reactor fuel, including MOX, or dedicated experimentation on fuel in French or foreign
test reactors. He has authored or co-authoredmore than 40 publications and book chapters.
Stéphanie Pellegrino, CEA Senior Expert on
accelerators specializing in the interaction of radiation with matter and damage due to radiation.
She holds a PhD in radiation effects in nuclear
ceramic materials (carbides). Engineer and lecturer for 24 years at INSTN. She has authored andco-authored over 30 scientific articles in peer-reviewed journals. In 2004, she was awarded theJacques Gaussens Prize for the young researcherof the year. She has been working on accelerators for 24 years and she practices several
methods of material characterization such as
ion beam analysis (RBS, ERDA, PIXE and NRA),
Raman spectroscopy as well as metallurgicalcharacterizations (hardness test, XRD, tensiletest). She has participated to numerous international symposiums or workshops as lecturer oras chairman.
Christian Sorel, CEA International Expert andAssociated Professor at INSTN. He has been
involved for more than 25 years in the modelling and the flowsheet design of separation
processes by solvent extraction devoted to therecovery and the purification of metals (actinides,rare earths and other strategic materials). He is
the author (or co-author) of more than 30 papers
published in peer-re- viewed international journals and 7 patents.
Etienne Studer is International Expert at the CEA
in fluid mechanics and hydrogen risk issues. He
has 30 years of experience working in the fieldof hydrogen risk in nuclear power plants. He iscurrently involved in experimental programmes(MISTRA facility) and model- ling activities(CAST3M CFD code). He has participated tointernational experimental programmes, international working groups and state-of-the-art reports. He takes part to the “European Hydrogen
Safety Panel”.
Jean Tommasi is Senior Expert at the CEA for fast
reactor neutron physics. He has been involvedin fast reactor core design and minor actinide
transmutation studies and is currently working in
the fields of code validation against experiments
and calculation methods. For several years now,
he has been active in tutorial classes on neutronics at INSTN. He authored or co-authored over
80 publications in these fields.
Jean-François Vidal is Senior Expert at the CEA
in neutronics. He has 30 years of experience indeveloping calculation schemes for various reactor applications (fast and thermal ones). He is currently responsible for the R&D of the APOLLO3
deterministic transport code developed at theCEA. He teaches transport methods at INSTN
and has authored or co-authored more than 50
publications in peer-reviewed journals and international conferences.
Andrea Zoia holds a MSc (2005) and a PhD(2008) in nuclear engineering from Politecnico di
Milano (Italy). Since 2008 he has been working at
the CEA/Saclay, in the development team of theMonte Carlo transport code TRIPOLI-4, and heis currently Monte Carlo group leader. His main
research focus is on stochastic processes andMonte Carlo methods for eigenvalue problems
in reactor physics and for variance reduction inradiation shielding

COURTESY OF: CEA/DEN, AREVA • GÉOLANEMAINLECTURERS