M2 Nuclear Engineering

Frédéric FOUQUET (CEA/INSTN) Grégory CAPLIN (Orano) Mathieu MILIN (IRSN).

Because it is a prerequisite for the “Criticality-Safety” course the “Introduction to Safety” course is the first to be taught in the module.

The 12-hour “Introduction to Safety” part consists of a 11-hour “course” part and a 1-hour “course-tutorial” part each addressed to the full-class. The 12-hour “Criticality-Safety” part consists of a 6-hour “course” part addressed to the full-class, a 3-hour “course-tutorial” part addressed to the half-class (two student groups), and a 3-hour “tutorial” part addressed to the half-class . Such modalities strength the interaction students/teachers and make the learning more effective.

The all nuclear activity sectors are interested by the operationnal problematics of the Safety and Criticality-Safety treated.
1.Introduction to Safety

Introduction
•Deterministic approa
•Safety barriers and functions
•Accident classification
•Design Basic Accident
•Safety culture, organization & quality
•Practical example : Study of a Loss Of Coolant Accident

Operation and Safety
•International standards
•General Operating Rules, Operating Technical Specifications,
•Emergency procedure
•Periodic safety review
•Maintenance management

Probabilistic safety assessment
•Probabilistic Risk Assessment
•Safety goals
•Event/fault tree
•Strengths & limitations

Emergency preparedness
•Crisis organization in France
•Emergency preparedness response
•On-site emergency plans / off-site emergency plans
•Dispersion model

Enhancing safety
•Beyond Design Basic Accident
•Internal & external hazards
•TMI, Tchernobyl, Fukushima scenarios
•Post-Fukushima action plan
•Experience feedback for the EPR

2. Criticality-Safety

- To understand the consequences and the phenomenology of an inadvertent criticality in a fuel cycle facility (except operating nuclear cores) or during a transport of fissile materials,
- To know how to prevent the occurrence a criticality accident (methods of control, double contingency principle, safety assessment, calculation methods and hypotheses, margins of subcriticality…) and how to limit the consequences of such an accident, should it occurs.

Prerequisites for « Introduction to Safety »: Basic knowledge on PWR (components, systems and operation).

Prerequisites for « Criticality-Safety »: Basics Neutronics. « Introduction to Safety » course is also a prerequisite.

1. “Introduction to Safety” part:

IAEA website : « safety of nuclear power plants » documents •https://www.iaea.org/search/google/safety%20of%20nuclear%20power%20plants •https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/3mile-isle.html

2.“Criticality-Safety” part:

* T.P. McLaughlin et Al., “A Review of Criticality Accidents”, 2000 Revision, LA-13638,

* “Analysis Guide – Nuclear Criticality Risks and their prevention in plants and laboratories”, DSU/SEC/T/2010-334, http://www.irsn.fr/EN/publications/technical-publications/Documents/IRSN_report_nuclear_criticality_risks.pdf.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Philippe MASSIOT (INSTN) François TROMPIER, Estelle Davesne (IRSN) Cheikh DIOP (CEA Saclay) Nathalie DRAY (Framatome).

This module consists of 28.5h/student. The teaching implements a wide range of pedagogical methods including labs, calculation codes and serious games, a training pilot facility. According to the pedagogical method used the class has to be divided into two 25-student groups or four 12-student groups.

Complete knowledge and operational skills in Radiation Protection are provided by implementing a wide range of approaches.

1. Using the international regulation frame of reference
- Identify the actor of international and national regulation (ICRP, IAEA, EU, ASN ...)
- Describe the radiation protection principles

2. Describe the main uses of radiation in various fields
- Categorize and explain the different types of radiation sources (natural and industrial).

3. Apply the three means of protection against ionizing radiation
- Apply radiation protection by reducing the exposed time, by setting up shielding, by increasing the distance.
- Determine the collective and personal protective equipment.

4. Characterize a workplace study:
-Apply and supervise workplace study.

5. Describe the external dosimetry concepts:
- Differentiate the efficiency of different shielding for different radiation.
- Calculate shielding manually and by using calculation code.

6. Apply the external dosimetric concepts:
- Assess and interpret external dosimetry.
- Apply the different operational and protection quantities used for dosimetry.
- Apply deterministic and/or Monte-Carlo method to resolve transport equation.

7. Explain the principles of internal dosimetry:
- Describe the physical aerosol aspects and kinetic biological models.

8. Identify the biological effects of ionizing radiation:

9. Use different detection devices:

10. Study the accidental / incidental situations:.

Nuclear physics: radioactivity, emission intensity, directly and indirectly ionizing particles, beta particles, x-rays, gamma-rays, cross sections of interaction. - Interaction of radiation with matter: • Interaction of photon with matter: •Interaction of light and heavy charge particles with matter •Interaction of neutrons with matter: elastic and inelastic scattering, capture, fission, transmission law.

- Introduction to radiological physics and radiation dosimetry, F. H. Attix, Wiley, 1986. - ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. Oxford: Elsevier; ICRP Publication 103; 2007. - Knoll, G. F. Radi.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Gilles MATHONNIERE (CEA Saclay). A compléter.

This 15-hour module is divided into five three-hour slots. Each slot is devoted to one part of the course.

The educational objective of this teaching module is to raise student’s awareness to the flexibility aspects which will have an increasingly influential role especially for electricity. The complementarity of variable renewable energy sources (VRE) and nuclear will be addressed both technically and economically.
This teaching module is divided into 5 parts:
•The global energy situation. Trends will be highlighted: slowing down the use of fossil energy and a fast increase in electricity demand. As this electricity has to be as decarbonated as possible, the electricity mix will rely mainly on VRE, hydraulics and nuclear.

•The power electric grid, flexibility, the future role of nuclear power. Presentation of the electrical network and its various constraints to function properly. Presentation and discussion on the future decarbonated electrical mix, the flexibility of nuclear power will play a leading role. Some ways of improvement for the future will also be mentioned (SMR, PWR without boron, Fast reactors).

•Economic aspects. The consequences from an economic point of view are analyzed.

•The cogeneration. Presentation of the heat market, heat distribution networks, the potential of nuclear reactors in this field and some feedback from projects carried out abroad.

•Hydrogen production. Presentation of the hydrogen market, the cost of hydrogen production by electrolysis and the possibility of finding a business model for a nuclear reactor based on both the production of electricity and hydrogen.

No specific prerequisite. Interest for both economy and electricity supply is desirable.

•The costs of Decarbonisation : System Costs with High Shares of Nuclear and Renewables OECD/NEA •Projected Costs of Electricity Generation IEA/NEA •Cany, C., Mansilla, C., Mathonnière, G., & da Costa, P. (2018a). Nuclear contribution to the penetration of variable renewable energy sources in a French decarbonised power mix. Energy, 150, 544–555. •Leurent, M., Jasserand, F., Locatelli, G., Palm, J., Rämä, M., & Trianni, A. (2017). Driving forces and obstacles to nuclear cogeneration in Europe: Lessons learnt from Finland. Energy Policy, 107, 138–150. •Tlili, O., Cany, C

Janvier - Février - Mars.

GIF-SUR-YVETTE

Pascal DANNUS (CEA.INSTN) Frédéric DAMIAN, Richard LENAIN, Jean-Baptiste THOMAS (CEA/DEN).

1.Nuclear Fuel Cycles part: The 6h of “course-tutorial” (“cours-TD” in French) slots will be delivered by two teachers together in front of the full class. The 3h of tutorial (“TD” in French) will be addressed 2 half-class (2 groups of students) in parallel. 2.Nuclear Reactor Systems part: 18 h of “course-tutorial” will be delivered at a time. Three teachers are successively involved with the following distribution: a.Introduction, Gen-IV, Design and Prospects (J.B. Thomas) b.Gen-IV HTR, Gen-I reactors (including Gas-cooled reactors, heavy water reactors and RBMK), Experimental Reactors (R. Lenain) c.Gen-III including BWR, Innovation and Multi-recycling, toward Gen-IV nuclear fleet (F. Damian).

1.Nuclear Fuel Cycles :
•To highlight the strong links between the LWR features and its fuel in order to determine the right front-end
steps needed to produce the convenient fuel as well as its amount.
•To underline the costs related to each front-end step and to identify the leeway to reduce them.
•To identify the disposal ways regarding to the category of nuclear waste.
•To compare the “once-through” and the “reprocessing-recycling” back-end options by taking into account the
capacities to save uranium resources, the capacities to reduce the volume and the radiotoxicity of nuclear
waste.

2.Nuclear Reactor Systems
• To provide a general vision of the main nuclear reactor designs and systems, including the Small Modular Reactors (SMR) and Molten Salt Reactors (MSR)
•From the descriptive and historical knowledge of the nuclear reactor systems, identifying the strengths & weaknesses of designs dedicated to specific priorities.
•From the dynamic analysis of the last decades (depending on the forces acting within the energy field): identify the main drivers leading to the present situation and trends.
•Combining critical constraints (safety, competitiveness, proliferation resistance, rise of intermittent power sources) with mean term requirements (resources and waste management) in order to become able to contribute proposing relevant fuel cycle and reactor development options and schedule.

Basics of U chemistry. Basics of Radiation Protection. PWR functional description. Basics of system thermodynamics, of neutronics, thermal hydraulics, fuel cycle.

“Treatment and recycling of spent nuclear fuel; actinide partitioning – Application to waste management”, Monographie CEA/DEN, Editions Le Moniteur, 2008 “Nuclear Reactor Systems”, collection Génie Atomique, EDP Sciences (2016) Several books from Monographie CEA/DEN, Editions Le Moniteur, each of them dedicated to a specific system.

Novembre - Décembre.

GIF-SUR-YVETTE

Louis-Joseph BONNAUD (CEA/INSTN) Experts EDF, Framatome.

This 24-hour module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

It consists of 21h of courses addressed to the full-class and 3h of tutorial addressed to half-class (two groups). After following the teachings of the module, students will be able to describe the general organization of PWR in the context of a normal operation including: -the functional role of the components of the nuclear island as well as the main physical phenomena associated; -nuclear auxiliary fluid systems; -the conventional island. They will have assimilated the economic issues related to the thermodynamic performance of water-steam conversion cycle, security and economic issues related to the fuel and its management. The concepts of Burn Up, hotspot factor, loading pattern associated with safety criteria are thoroughly described.

This module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

-Architecture and components
•The1300 MWe PWR and function of each component of the RCS, including the vessel, the core, the fuel assemblies, the RCCA, the pumps, the pressurizer, the steam generator, the containment building and the nuclear auxiliary building
•The different stages of refueling and identify the spent fuel pool, the storage racks, the fuel transfer device, the refueling cavity…
-Main auxiliary systems
•Chemical and volume control system, reactor boron and water makeup system, residual heat removal system, spent fuel pit cooling and treatment system
•Main function performed, the basic flow diagram and the operation of these systems
-The nuclear fuel
•Market and stakes of the nuclear fuel
•The fuel assembly
•Cladding integrity, its reliability and the feedback on it
•Reactivity control including control rods, soluble boron and burnable poisons
•The core-loading pattern with goal and stakes
-Thermodynamic cycle: design and performance
•Thermodynamic cycle of a PWR and and the different ways to improve the energy efficiency
•Thermodynamic cycle and the industrial tools allowing to calculate it.

General physics, thermodynamics, fluid mechanism and heat transfert.

Barré, B. et al. (2016). Nuclear Reactor Systems. Edp Sciences. Reuss, Paul (2008). Neutron physics. Edp Sciences.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

FANG Yiping, ZENG Zhiguo, FAURIAT William, HIBTI Mohammed, DUVAL Carole.

The course will be given at INSTN.

Objectives:
The course illustrates the mathematical modelling and system simulation methods for evaluating, managing and controlling the reliability, safety and risk of nuclear systems. The objective is to provide the students with
the adequate tools for handling with scientific rigor the complexities and uncertainties associated to the problem. The prerequisite is knowledge on basic probability theory and statistics. The expertise offered is part of the background knowledge of safety, reliability and risk analysts, operators and managers, in the nuclear sector.
Practical examples and quantitative exercises will be provided in support to the comprehension of the material covered in class.

Contents:
- Definition of reliability, safety, risk; structure of risk analysis
- Hazard identification: functional analysis, Hazard Operability (HAZOP) analysis and Failure Modes, Effects and Criticality Analysis (FMECA)
- Fault tree and event tree analysis
- Markov models for reliability and availability analysis
- Bayesian belief networks for reliability and risk analysis
- Petri nets and Boolean logic Driven Markov Processes (BDMP) for reliability and risk analysis
- Monte Carlo simulation for reliability and risk analysis
- Human factors
- Organizational factors
- Probabilistic Risk Assessment (PRA).

Probability, Statistics.

Zio E., An introduction to the basics of reliability and risk analysis, World Scientific, 2007. Zio E., Computational methods of reliability and risk analysis, World Scientific, 2009. Zio, E. Baraldi, P. and Cadini F., Basics of reliability and risk analysis: Worked Out Problems and Solutions, World Scientific, 2011.

Septembre - Octobre - Novembre - Décembre - Janvier.

Saclay

Frédéric FOUQUET (CEA/INSTN) Grégory CAPLIN (Orano) Mathieu MILIN (IRSN).

Because it is a prerequisite for the “Criticality-Safety” course the “Introduction to Safety” course is the first to be taught in the module.

The 12-hour “Introduction to Safety” part consists of a 11-hour “course” part and a 1-hour “course-tutorial” part each addressed to the full-class. The 12-hour “Criticality-Safety” part consists of a 6-hour “course” part addressed to the full-class, a 3-hour “course-tutorial” part addressed to the half-class (two student groups), and a 3-hour “tutorial” part addressed to the half-class . Such modalities strength the interaction students/teachers and make the learning more effective.

The all nuclear activity sectors are interested by the operationnal problematics of the Safety and Criticality-Safety treated.
1.Introduction to Safety

Introduction
•Deterministic approa
•Safety barriers and functions
•Accident classification
•Design Basic Accident
•Safety culture, organization & quality
•Practical example : Study of a Loss Of Coolant Accident

Operation and Safety
•International standards
•General Operating Rules, Operating Technical Specifications,
•Emergency procedure
•Periodic safety review
•Maintenance management

Probabilistic safety assessment
•Probabilistic Risk Assessment
•Safety goals
•Event/fault tree
•Strengths & limitations

Emergency preparedness
•Crisis organization in France
•Emergency preparedness response
•On-site emergency plans / off-site emergency plans
•Dispersion model

Enhancing safety
•Beyond Design Basic Accident
•Internal & external hazards
•TMI, Tchernobyl, Fukushima scenarios
•Post-Fukushima action plan
•Experience feedback for the EPR

2. Criticality-Safety

- To understand the consequences and the phenomenology of an inadvertent criticality in a fuel cycle facility (except operating nuclear cores) or during a transport of fissile materials,
- To know how to prevent the occurrence a criticality accident (methods of control, double contingency principle, safety assessment, calculation methods and hypotheses, margins of subcriticality…) and how to limit the consequences of such an accident, should it occurs.

Prerequisites for « Introduction to Safety »: Basic knowledge on PWR (components, systems and operation).

Prerequisites for « Criticality-Safety »: Basics Neutronics. « Introduction to Safety » course is also a prerequisite.

1. “Introduction to Safety” part:

IAEA website : « safety of nuclear power plants » documents •https://www.iaea.org/search/google/safety%20of%20nuclear%20power%20plants •https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/3mile-isle.html

2.“Criticality-Safety” part:

* T.P. McLaughlin et Al., “A Review of Criticality Accidents”, 2000 Revision, LA-13638,

* “Analysis Guide – Nuclear Criticality Risks and their prevention in plants and laboratories”, DSU/SEC/T/2010-334, http://www.irsn.fr/EN/publications/technical-publications/Documents/IRSN_report_nuclear_criticality_risks.pdf.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Philippe MASSIOT (INSTN) François TROMPIER, Estelle Davesne (IRSN) Cheikh DIOP (CEA Saclay) Nathalie DRAY (Framatome).

This module consists of 28.5h/student. The teaching implements a wide range of pedagogical methods including labs, calculation codes and serious games, a training pilot facility. According to the pedagogical method used the class has to be divided into two 25-student groups or four 12-student groups.

Complete knowledge and operational skills in Radiation Protection are provided by implementing a wide range of approaches.

1. Using the international regulation frame of reference
- Identify the actor of international and national regulation (ICRP, IAEA, EU, ASN ...)
- Describe the radiation protection principles

2. Describe the main uses of radiation in various fields
- Categorize and explain the different types of radiation sources (natural and industrial).

3. Apply the three means of protection against ionizing radiation
- Apply radiation protection by reducing the exposed time, by setting up shielding, by increasing the distance.
- Determine the collective and personal protective equipment.

4. Characterize a workplace study:
-Apply and supervise workplace study.

5. Describe the external dosimetry concepts:
- Differentiate the efficiency of different shielding for different radiation.
- Calculate shielding manually and by using calculation code.

6. Apply the external dosimetric concepts:
- Assess and interpret external dosimetry.
- Apply the different operational and protection quantities used for dosimetry.
- Apply deterministic and/or Monte-Carlo method to resolve transport equation.

7. Explain the principles of internal dosimetry:
- Describe the physical aerosol aspects and kinetic biological models.

8. Identify the biological effects of ionizing radiation:

9. Use different detection devices:

10. Study the accidental / incidental situations:.

Nuclear physics: radioactivity, emission intensity, directly and indirectly ionizing particles, beta particles, x-rays, gamma-rays, cross sections of interaction. - Interaction of radiation with matter: • Interaction of photon with matter: •Interaction of light and heavy charge particles with matter •Interaction of neutrons with matter: elastic and inelastic scattering, capture, fission, transmission law.

- Introduction to radiological physics and radiation dosimetry, F. H. Attix, Wiley, 1986. - ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. Oxford: Elsevier; ICRP Publication 103; 2007. - Knoll, G. F. Radi.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Gilles MATHONNIERE (CEA Saclay). A compléter.

This 15-hour module is divided into five three-hour slots. Each slot is devoted to one part of the course.

The educational objective of this teaching module is to raise student’s awareness to the flexibility aspects which will have an increasingly influential role especially for electricity. The complementarity of variable renewable energy sources (VRE) and nuclear will be addressed both technically and economically.
This teaching module is divided into 5 parts:
•The global energy situation. Trends will be highlighted: slowing down the use of fossil energy and a fast increase in electricity demand. As this electricity has to be as decarbonated as possible, the electricity mix will rely mainly on VRE, hydraulics and nuclear.

•The power electric grid, flexibility, the future role of nuclear power. Presentation of the electrical network and its various constraints to function properly. Presentation and discussion on the future decarbonated electrical mix, the flexibility of nuclear power will play a leading role. Some ways of improvement for the future will also be mentioned (SMR, PWR without boron, Fast reactors).

•Economic aspects. The consequences from an economic point of view are analyzed.

•The cogeneration. Presentation of the heat market, heat distribution networks, the potential of nuclear reactors in this field and some feedback from projects carried out abroad.

•Hydrogen production. Presentation of the hydrogen market, the cost of hydrogen production by electrolysis and the possibility of finding a business model for a nuclear reactor based on both the production of electricity and hydrogen.

No specific prerequisite. Interest for both economy and electricity supply is desirable.

•The costs of Decarbonisation : System Costs with High Shares of Nuclear and Renewables OECD/NEA •Projected Costs of Electricity Generation IEA/NEA •Cany, C., Mansilla, C., Mathonnière, G., & da Costa, P. (2018a). Nuclear contribution to the penetration of variable renewable energy sources in a French decarbonised power mix. Energy, 150, 544–555. •Leurent, M., Jasserand, F., Locatelli, G., Palm, J., Rämä, M., & Trianni, A. (2017). Driving forces and obstacles to nuclear cogeneration in Europe: Lessons learnt from Finland. Energy Policy, 107, 138–150. •Tlili, O., Cany, C

Janvier - Février - Mars.

GIF-SUR-YVETTE

Pascal DANNUS (CEA.INSTN) Frédéric DAMIAN, Richard LENAIN, Jean-Baptiste THOMAS (CEA/DEN).

1.Nuclear Fuel Cycles part: The 6h of “course-tutorial” (“cours-TD” in French) slots will be delivered by two teachers together in front of the full class. The 3h of tutorial (“TD” in French) will be addressed 2 half-class (2 groups of students) in parallel. 2.Nuclear Reactor Systems part: 18 h of “course-tutorial” will be delivered at a time. Three teachers are successively involved with the following distribution: a.Introduction, Gen-IV, Design and Prospects (J.B. Thomas) b.Gen-IV HTR, Gen-I reactors (including Gas-cooled reactors, heavy water reactors and RBMK), Experimental Reactors (R. Lenain) c.Gen-III including BWR, Innovation and Multi-recycling, toward Gen-IV nuclear fleet (F. Damian).

1.Nuclear Fuel Cycles :
•To highlight the strong links between the LWR features and its fuel in order to determine the right front-end
steps needed to produce the convenient fuel as well as its amount.
•To underline the costs related to each front-end step and to identify the leeway to reduce them.
•To identify the disposal ways regarding to the category of nuclear waste.
•To compare the “once-through” and the “reprocessing-recycling” back-end options by taking into account the
capacities to save uranium resources, the capacities to reduce the volume and the radiotoxicity of nuclear
waste.

2.Nuclear Reactor Systems
• To provide a general vision of the main nuclear reactor designs and systems, including the Small Modular Reactors (SMR) and Molten Salt Reactors (MSR)
•From the descriptive and historical knowledge of the nuclear reactor systems, identifying the strengths & weaknesses of designs dedicated to specific priorities.
•From the dynamic analysis of the last decades (depending on the forces acting within the energy field): identify the main drivers leading to the present situation and trends.
•Combining critical constraints (safety, competitiveness, proliferation resistance, rise of intermittent power sources) with mean term requirements (resources and waste management) in order to become able to contribute proposing relevant fuel cycle and reactor development options and schedule.

Basics of U chemistry. Basics of Radiation Protection. PWR functional description. Basics of system thermodynamics, of neutronics, thermal hydraulics, fuel cycle.

“Treatment and recycling of spent nuclear fuel; actinide partitioning – Application to waste management”, Monographie CEA/DEN, Editions Le Moniteur, 2008 “Nuclear Reactor Systems”, collection Génie Atomique, EDP Sciences (2016) Several books from Monographie CEA/DEN, Editions Le Moniteur, each of them dedicated to a specific system.

Novembre - Décembre.

GIF-SUR-YVETTE

Louis-Joseph BONNAUD (CEA/INSTN) Experts EDF, Framatome.

This 24-hour module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

It consists of 21h of courses addressed to the full-class and 3h of tutorial addressed to half-class (two groups). After following the teachings of the module, students will be able to describe the general organization of PWR in the context of a normal operation including: -the functional role of the components of the nuclear island as well as the main physical phenomena associated; -nuclear auxiliary fluid systems; -the conventional island. They will have assimilated the economic issues related to the thermodynamic performance of water-steam conversion cycle, security and economic issues related to the fuel and its management. The concepts of Burn Up, hotspot factor, loading pattern associated with safety criteria are thoroughly described.

This module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

-Architecture and components
•The1300 MWe PWR and function of each component of the RCS, including the vessel, the core, the fuel assemblies, the RCCA, the pumps, the pressurizer, the steam generator, the containment building and the nuclear auxiliary building
•The different stages of refueling and identify the spent fuel pool, the storage racks, the fuel transfer device, the refueling cavity…
-Main auxiliary systems
•Chemical and volume control system, reactor boron and water makeup system, residual heat removal system, spent fuel pit cooling and treatment system
•Main function performed, the basic flow diagram and the operation of these systems
-The nuclear fuel
•Market and stakes of the nuclear fuel
•The fuel assembly
•Cladding integrity, its reliability and the feedback on it
•Reactivity control including control rods, soluble boron and burnable poisons
•The core-loading pattern with goal and stakes
-Thermodynamic cycle: design and performance
•Thermodynamic cycle of a PWR and and the different ways to improve the energy efficiency
•Thermodynamic cycle and the industrial tools allowing to calculate it.

General physics, thermodynamics, fluid mechanism and heat transfert.

Barré, B. et al. (2016). Nuclear Reactor Systems. Edp Sciences. Reuss, Paul (2008). Neutron physics. Edp Sciences.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Doligez Xavier, Université Paris-Saclay.

The course is divided in 8 session of 3 hours each. For each session, a lecture will be given on the topic at hand followed immediately by a tutorial session in which the students use the new concepts in samples problems.

This course aims to give enough understanding of the neutronics to be able to understand results and challenges of neutronics studies. The sessions will cover:
1. Review of nuclear physics basics: size, charge and mass of the nucleus . binding energy in ground state nuclei and excitation energy. radioactive decays : alpha, beta and gamma decay. Special focus on telluric decays chains. Exothermic and endothermic reactions,.
2. Cross-sections: microscopic and macroscopic; mixtures; angular, differential and multi reactions.
3. Nuclear fission: fissile and fertile nuclei, competition with other reactions. fission products, neutrons and gamma rays emitted.
4. Neutron chain reactions: concepts of criticality and reactivity.
5. Neutron Diffusion: neutron flux and diffusion equation. effect of boundary conditions and extrapolation distance.
6. Depletion due to neutronic irradiation : Bateman equation. breeding and conversion ratio.
7. Reactor kinetics: evolution of neutron population. prompt kinetics. impact of delayed neutrons.
8. External influences on reactivity: temperature, loss of moderation, control and safety rods; burn-up of the fuel.

Students should be familiar with basic concepts of nuclear physics such as: size, charge and mass of the nucleus; the binding energy in ground state nuclei; excitation energy. They should understand radioactive decays.

Students should be familiar with derivatives of common analytic function and have sufficient knowledge in mathematics to solve simple linear differential equation of the first and second order.

Septembre - Octobre - Novembre - Décembre - Janvier.

GIF-SUR-YVETTE

Fadhel MALOUCH (CEA Saclay).

This course takes place in 9 sessions (of 3 hours each) and which correspond to the items defined above. The coordinator of the teaching unit provides all lectures. No duplication of the group of students is to be expected. Examples of applications are inserted in the lecture sessions for a better assimilation the discussed concepts.

The objective of this course is to provide the basics of neutronics and reactor physics for the design and the operation of nuclear reactors. The course aims at describing the physical phenomena that make it possible to apprehend reactor-core control and associated aspects (neutron transport, safety-criticality, kinetics, reactivity, control means, etc.).

•Review of nuclear physics basics
•Introduction to neutron physics
•Criticality aspects
•Kinetic aspects, point kinetics and chain reaction equations
•Reactivity variations (fuel evolution, fission products and temperature effects)
•Reactor control
•The transport equation
•The diffusion equation
•Multigroup theory (space-energy coupling).

Linear Algebra, Differential Equation.

Paul Reuss, “Neutron Physics”, Les Ulis, INSTN/EDPSciences, 2008. “Neutronics”, A Nuclear Energy Division Monograph", ouvrage collectif, Paris, Saclay, Les Éditions du Moniteur/CEA, 2015.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Nicolas DORVILLE, Patrick DUMAZ (CEA).

There are eleven 3-hour time slots. The teaching is delivered according to a “course-tutorial” mode allowing a strong participation of the students and an effective interaction with the teachers. In addition, some home-works, associated with an assessment, constitute a part of the Modalities of Knowledge Assessment process. A final written exam completes the assessment process.

- Fluid mechanics
Control volumes and control masses. Balance equations: instantaneous, Integral forms, local equations, 1D equations, lumped equations. Resolution for simple laminar conditions. Dimensional analysis
Turbulent flows: introduction on statis.

Basics Math knowledge is necessary for this course: integrals and derivatives, vectors and tensors.

-The teacher will provide a textbook with all the necessary information. -N.E. Todreas, M.S. Kazimi, Nuclear systems I, Thermal Hydraulic Fundamentals, Taylor&Francis.

Septembre - Octobre.

GIF-SUR-YVETTE

Xavier VITART (CEA), Frédérique HOURCADE (Orano), Muriel FIRON (CEA).

All the lessons are performed by professionals (CEA, ORANO, EDF, ANDRA companies), deeply involved in Decommissioning and Waste Management projects or R&D activities in the field. The pedagogical methods ara funded on learning by problems and by projects, with a high level of implication of the students, through interactions with the teachers, and through projects studies in groups. Visits are organised in order to confrontate the students with the field realities.

The aim of this module is to give the students an overview of all the components of the decommissioning of nuclear facilities process, from an engineering point of view, meaning puridisciplinary, multi-scale, systemic approaches, meaning how to apprehend complexity. Lessons include regulatory and safety issues, project management (different steps which have to be teaken into account), how to built a scenario of decommissioning, risk analysis, safety studies, ALARA (As low as reasonably achivable) principle, instrumentation and detection methods, research and development activities in the field (news tools, new methods, new strategies), human and organizational factors of success, cost evaluation based on experience feedback. All the lessons include detailed real cases studies.

Pre-requisite are the fundamentals of the engineering sciences (physics, chemical engineering, mechanical engineering), and a good knowledge of the fundamentals of radioactivity (from the nature of radioactivity emissions to basic principles of radioprotection).

- Policies and Strategies for the Decommissioning of Nuclear and Radiological Facilities IAEA Nuclear Energy Series NW-G-2.1 - Guide de l'ASN n°6 : Arrêt définitif, démantèlement et déclassement des installations nucléaires de base - Guide n°14 de l'ASN r.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Yohan RENUCCI (CEA) Patrice FRANCOIS (IRSN) Laure BRU (EDF) Jean-Marie RONDEAU Patrick O’SULLIVAN (AIEA) Thibaut NICOLAS (CEA).

Objectives
The aim of this course is to give the students an overview on the differents laws and regulations applicable for dismantling, decommisioning and waste management operations. The course gives a focus on French, European and international regulations.
Several opinions are considered from the electric provider company to the waste deposit manager.

Content
International regulations on nuclear waste management, French regulations on nuclear waste management, French nuclear industry organization : roles and responsibilities of the different actors, International collaboration on nuclear industry, Nuclear waste classification and packaging,
Authorizations and administrative organization.

Septembre - Octobre - Novembre - Décembre.

Ecole des Ponts ParisTech (Champs sur Marne)

Daniela Cancila.

Dependability of computer-based systems
The purpose of the lecture is to provide a theoretical and pragmatic knowledge of the dependability of computer-based systems. The way it impacts the architecture of computer-based systems as well as the design of their software will be described. The typical application is the computer-based Instrumentation & Control infrastructure of nuclear power plants: the history of stages and technical evolutions of French PWR I&C Design will be described as well as the structure of the control-command N4 I&C system (1450 MW) and the software aspects of the protection system.
Model-Checking is one major technique of automatic verification of computer-based control systems. It automatically checks and proves that a system, or a mathematical model of a system, validates some safety properties formalized within a temporal logic. Many case studies will be presented to students and many labs will be proposed.

Basic knowledge in software engineering and programming.

Janvier - Février.

PALAISEAU

Didier Schoevaerts, F Lignini, M Pfeiffer, P Videlaine, B Lenogue, M Vaindirlis, A Chabod, C Duval, B-J Willey, A Wasylyk, J Grosmaire.

CM: 39h

Session 1 : Mid Term examination (written or oral) (0,5) Final examination (Written or oral) (0,5)

Session 2 : Final examination (written or oral) (1).

Objectives:

-Explain the main general bases of the design of a nuclear power plant, the equipment and the systems, taking into account the nuclear safety requirements, the design codes and standards with their recent evolutions (regulatory and industrial context)
-Describe the architecture of the systems and the equipments of the nuclear installations and the associated instrumentation and control features
-Describe the rules for selecting of nuclear sites and their environment
-Describe the provisions taken in the design relative to radiation protection issues.

Janvier - Février - Mars.

PALAISEAU

Yves Crolet, Pierre-Alain Naze, Elie Petre-Lazar.

Janvier - Février - Mars.

PALAISEAU

Jean-Francois Semblat.

The organization of the various topics is described above. The course will alternate lectures with tutorials. Videos from a MOOC in the same field will also be used. The evaluation will be made through a seismic design project.

This course ranges from the science of earthquakes (seismology) to their effect on civil engineering structures (earthquake engineering). It is organized as follows:
1.Seismicity of the Earth and wave radiation by faults.
2.Seismic wave propagation: elastic waves and wave conversion.
3.Surface waves and seismic wave amplification: from theory to practice.
4.Soil dynamics and wave attenuation.
5.Dynamic soil-structure interaction.
6.Seismic response of structures: the response spectrum.
7.Seismic response of equipments.
8.Nonlinear seismic response of soils and structures.
9.Principles of seismic isolation.

Fundamentals of: •mechanics of solids and structures, •waves and vibrations. Basics in numerical methods.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Jean-Michel Torrenti, Adelaide Ferraille, Christophe Bernard, Benjamin Terrade.

6 courses (at ENSTA and Ifsttar) + 2 practical works (at Ifsttar).

1) Constructive principles of reinforced and prestressed concrete, example of the nuclear confinement vessels ·
2) Constitutive materials of concretes: cement, aggregates, water, admixtures, additions ·
3) Rheology of fresh concrete:
4) Mechanical behavior of the hardened concrete,
5) Delayed strains : shrinkage, creep
Practical Works 1: Manufacture of a concrete formulated during the course (compression sample + reinforced beam)
6) Durability of concrete
7) Modern concretes
8) Mechanical behavior and durability of steel in concrete structures
Practical Works 2: 28 days after part 1, compression and splitting tests on samples and loading of the beam in flexure.
2) les pre?-requis:.

Mechanics of material.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Kevin Ogle.

Janvier - Février - Mars.

PALAISEAU

Ioannis Politopoulos, Emmanuel Jeanvoine.

CM: 6h, TD: 12h, Projet: 15h.

Master the fundamental aspects of the finite elements methods and practice it in the context of the design of structures. Learn the different numerical algorithms especially those used in non-linear analysis of structures. Be able to solve highly non linear coupled problem with a degree of precision difficult to reach by classical methods (This fact is fundamental for the nuclear domain).
The students will be trained to write system of partial derivative equations associated with an actual problem from the nuclear domain, solve it numerically using a powerful finite elements software.
Each lesson is divided as follows: first the theoretical aspects associated with the studied phenomena is recalled, second its numerical treatment is specified and finally somes examples, will be solved using the finite elements software « Cast3m 2000 » and interpret the obtained results.

Good level in applied mathematics (analysis, algebra, optimization) Basic knowledge in software engineering and programming Elasticity (3D, beams, plates and shells) Heat conduction Plasticity Linear dynamics Non-linear dynamics Fatigue and fracture.

Janvier - Février - Mars.

PALAISEAU

M. Maloubier.

Five lectures and a bibliographic study.

The chemical properties of actinides element are described and related to their electronic characteristics. This course will cover the electronic structure (crystal field model and molecular orbitals) and their associated spectroscopic properties. The primary focus will be on understanding their spectroscopic properties (UV-Vis, fluorescence, and X-ray absorption) with the goal of understanding the speciation of actinides in different media. The notion will be introduced through the discussion of actinide behavior in the environment.

The goal of the course is to provide students with an understanding of the actinide elements for support in graduate education and/or research.

The course objectives are:
-Understanding the impact of f-orbitals on actinide chemistry
-Learn benefits of several spectroscopy techniques to determine the speciation of actinides (element specific, concentration range, etc.)
-Ability to interpret spectroscopy of actinides in term of physico-chemical speciation
-Understand the impact of the actinide speciation on their behavior in different environmental reservoir.

Quantum chemistry, electronic structure.

Septembre - Octobre - Novembre - Décembre.

PARIS

S. Delpech, G. Lefèvre.

This module deals with the chemistry of (1) molten salts, and (2) cooling circuits of PWR. Several common points exist, as a strong analogy with solution chemistry at room temperature.

The objective of the first part is to present the potential of pyrochemistry for nuclear fuel processing in general and for the particular case of the molten salt nuclear reactor (Generation IV reactor).
1.Basics of nuclear energy and describes Generation IV reactors and the molten salt reactor.
2.The chemistry of molten salts, their specific properties, the methodology of calculating thermodynamic diagrams of species stability as a function of potential and acidity (analogous to Pourbaix diagrams in aqueous solution).
3.Methods of separation/extraction by pyrochemical means (reductive extraction, use of oxidizing or reducing gases, precipitation of metal oxides, electro-reduction of metals) by a classical analytical chemistry approach in order to determine partition coefficients and to calculate extraction efficiencies and separation selectivity.
4.Some industrial processes using molten salts in the nuclear fuel cycle.

In the second part, the control of the chemistry of the primary and secondary circuits of PWR is presented.
1.Chemistry of primary circuit: composition, contamination concern, hydrothermal chemistry
2.Chemistry of secondary circuit: composition, corrosion and fouling concerns
3.Calculations of speciation at high temperature using Phreeqc software.

Solution chemistry.

Octobre - Novembre - Décembre.

PARIS

Fausto MALVAGI (CEA Saclay) Hervé GOLFIER (CEA Saclay).

The course is delivered successively by two teachers for the topics associated to transport theory and to reactor physics, respectively.

•Course : o Introduction to neutronics: 3h (Hervé GOLFIER)

•Cours-TD “Transport theory” part (Fausto MALVAGI): oTransport equation: 3h oOne-group diffusion: 6h oPoint kinetics: 3h oMultigroup theory: 3h oSlowing down and Resonant absorption: 6h

•Cours-TD “Reactor Physics” part (Hervé GOLFIER): oFission product poisoning: 3h oFuel depletion: 3h oTemperature effects and reactivity control: 6h

Homework exercises are given and a special exercise session is organized. Evaluation of knowledge and skills acquired though an exam.

The purpose of this course is to introduce the important elements for the understanding and the mastering of the physical phenomena governing the propagation of a neutron population in a multiplying system like a reactor.

•To provide knowledge on basic concepts of reactor physics and neutron life cycle.
•To give a general overview of neutronics through the fields of transport theory and reactor physics.
•To present the two fundamental equations which governs respectively the evolution in time of neutron
propagation and fuel depletion.
•To study the behavior of the neutron population with respect to the different variables of the phase-space of the linear Boltzmann equation:
oSpace and angle: transport theory versus diffusion theory;
oenergy: slowing down, resonance absorption, thermal scattering, multigroup formalism;
otime: point kinetics theory.
•To study basics reactor physics phenomena:
oBurnup effects :
?To analyze the impact of fission products presence in the nuclear fuel, and in particular the
phenomena of “fission product poisoning”.
?To investigate the fuel isotopical time evolution issues.
o Reactivity effects to understand the reactivity control mechanisms of a multiplying medium through :
?the material temperature effects;
?the material density effects.

Mathematics: differential equations, linear algebra, linear operators, probability. Basics of nuclear physics: nuclear reactions induced by neutrons, decay processes, cross-sections definitions, kinematics.

Paul Reuss, Neutron Physics, Les Ulis, INSTN/EDPSciences, 2008. J. J. Duderstadt, L. J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons, 1976.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Yann de Carlan, CEA Saclay Servane Coste, INSTN Aurélien Debelle, Université Paris-Sud, Université Paris-Saclay Frederico Garrido, Université Paris-Sud, Université Paris-Saclay Fabien Onimus, CEA Saclay Bertrand Reynier, ENSTA Paris.

Lectures as well as SEM and XRD are organized at INSTN Saclay; the JANNuS and SRIM labworks are performed at the CSNSM Lab (building 108, Orsay campus).

The aim of this course is to give an overall knowledge on the materials used in power nuclear reactors (Gen2&3 and innovative advanced reactors). The course describes the main materials used, for structural components, fuel cladding and fuel pellets. It addresses the main issues for nuclear applications such as radiation effects and corrosion. It is particularly focused on the detailed process of radiation damage at the microscopic scale. At a higher scale, the radiation effects on the main components (structure and fuel elements) will be detailed. The issue of in-reactor corrosion will be also described.

I Lectures and exercises
a-Atomic scale processes
b- Irradiation effects on various components of today’s nuclear reactors (Generations II and III )
c- Peculiar features of fuel of today’s nuclear reactors (Generations II and III )
d- Materials for innovative advanced reactors

II Labworks
a- Labwork at the JANNuS facilities and use of the SRIM simulation code
b- SEM and XRD labworks: Phase identification and steels microstructure identification.

Bachelor level in solid state physics and chemistry 6h hours of recall on pre-requisite on basics of materials science are provided at the beginning of the course.

Septembre - Octobre - Novembre - Décembre - Janvier.

ORSAY - GIF-SUR-YVETTE

Iolanda MATEA, Matthieu LEBOIS (Université Paris Saclay).

This course takes place during the first part of the Semester 3 of the Master, from mid-September to end of October. It alternates Tutorials to Lectures. The students are evaluated through a written examination of 3 hours.

This is a two part course: the first part is focused on introducing the essential tools of nuclear physics while the latter concentrates on their application for specific cases relevant to nuclear reactor physics.

The essential tools are comprised of cross sections, fundamental forces, mass, scales, the basic constituents of nuclear matter, nuclear potentials and the nuclear force; components of micro and macroscopic nuclear modelling and their relation to observed phenomenology; general two-body kinematics, nuclear reaction types and classifications.

The mainly atomic interaction of photons, protons, neutrons, alpha particles and electrons in matter provides the transition to the second part of the course.

The basic tools now taken as being acquired are used to understand spontaneous and induced radioactive growth and decay; alpha, beta, and gamma processes and modelling; the microscopic view of the neutron on different energy scales and specific reactor physics vocabulary, the basic fission process and an introduction to Breit-Wigner cross section resonance phenomenology.

This course, accompanied by a series of tutorials, should allow the student to discern between the different fundamental processes and dimensions, which are subsequently studied on the macroscopic scale within the context of material physics, neutronics, and the simulation of reactor evolution.

Mathematics: differential equations, linear algebra, linear operators, probability. Quantum Mechanics, Electrodynamics.

Kenneth S. Krane, Introductory Nuclear Physics, New York, John Wiley & Sons, Inc, 1988. A. Das and T. Ferbel, Introduction to Nuclear and Particle Physics, World Scientific, 2003. W. R. Leo, Techniques for Nuclear and Particle Physics Experiments – A How-to Approach, Springer-Verlag Berlin Heidelberg GmbH, 1994.

Septembre - Octobre.

GIF-SUR-YVETTE

Daniela Cancila.

Dependability of computer-based systems
The purpose of the lecture is to provide a theoretical and pragmatic knowledge of the dependability of computer-based systems. The way it impacts the architecture of computer-based systems as well as the design of their software will be described. The typical application is the computer-based Instrumentation & Control infrastructure of nuclear power plants: the history of stages and technical evolutions of French PWR I&C Design will be described as well as the structure of the control-command N4 I&C system (1450 MW) and the software aspects of the protection system.
Model-Checking is one major technique of automatic verification of computer-based control systems. It automatically checks and proves that a system, or a mathematical model of a system, validates some safety properties formalized within a temporal logic. Many case studies will be presented to students and many labs will be proposed.

Basic knowledge in software engineering and programming.

Janvier - Février.

PALAISEAU

Didier Schoevaerts, F Lignini, M Pfeiffer, P Videlaine, B Lenogue, M Vaindirlis, A Chabod, C Duval, B-J Willey, A Wasylyk, J Grosmaire.

CM: 39h

Session 1 : Mid Term examination (written or oral) (0,5) Final examination (Written or oral) (0,5)

Session 2 : Final examination (written or oral) (1).

Objectives:

-Explain the main general bases of the design of a nuclear power plant, the equipment and the systems, taking into account the nuclear safety requirements, the design codes and standards with their recent evolutions (regulatory and industrial context)
-Describe the architecture of the systems and the equipments of the nuclear installations and the associated instrumentation and control features
-Describe the rules for selecting of nuclear sites and their environment
-Describe the provisions taken in the design relative to radiation protection issues.

Janvier - Février - Mars.

PALAISEAU

Yves Crolet, Pierre-Alain Naze, Elie Petre-Lazar.

Janvier - Février - Mars.

PALAISEAU

Jean-Francois Semblat.

The organization of the various topics is described above. The course will alternate lectures with tutorials. Videos from a MOOC in the same field will also be used. The evaluation will be made through a seismic design project.

This course ranges from the science of earthquakes (seismology) to their effect on civil engineering structures (earthquake engineering). It is organized as follows:
1.Seismicity of the Earth and wave radiation by faults.
2.Seismic wave propagation: elastic waves and wave conversion.
3.Surface waves and seismic wave amplification: from theory to practice.
4.Soil dynamics and wave attenuation.
5.Dynamic soil-structure interaction.
6.Seismic response of structures: the response spectrum.
7.Seismic response of equipments.
8.Nonlinear seismic response of soils and structures.
9.Principles of seismic isolation.

Fundamentals of: •mechanics of solids and structures, •waves and vibrations. Basics in numerical methods.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Jean-Michel Torrenti, Adelaide Ferraille, Christophe Bernard, Benjamin Terrade.

6 courses (at ENSTA and Ifsttar) + 2 practical works (at Ifsttar).

1) Constructive principles of reinforced and prestressed concrete, example of the nuclear confinement vessels ·
2) Constitutive materials of concretes: cement, aggregates, water, admixtures, additions ·
3) Rheology of fresh concrete:
4) Mechanical behavior of the hardened concrete,
5) Delayed strains : shrinkage, creep
Practical Works 1: Manufacture of a concrete formulated during the course (compression sample + reinforced beam)
6) Durability of concrete
7) Modern concretes
8) Mechanical behavior and durability of steel in concrete structures
Practical Works 2: 28 days after part 1, compression and splitting tests on samples and loading of the beam in flexure.
2) les pre?-requis:.

Mechanics of material.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Kevin Ogle.

Janvier - Février - Mars.

PALAISEAU

Ioannis Politopoulos, Emmanuel Jeanvoine.

CM: 6h, TD: 12h, Projet: 15h.

Master the fundamental aspects of the finite elements methods and practice it in the context of the design of structures. Learn the different numerical algorithms especially those used in non-linear analysis of structures. Be able to solve highly non linear coupled problem with a degree of precision difficult to reach by classical methods (This fact is fundamental for the nuclear domain).
The students will be trained to write system of partial derivative equations associated with an actual problem from the nuclear domain, solve it numerically using a powerful finite elements software.
Each lesson is divided as follows: first the theoretical aspects associated with the studied phenomena is recalled, second its numerical treatment is specified and finally somes examples, will be solved using the finite elements software « Cast3m 2000 » and interpret the obtained results.

Good level in applied mathematics (analysis, algebra, optimization) Basic knowledge in software engineering and programming Elasticity (3D, beams, plates and shells) Heat conduction Plasticity Linear dynamics Non-linear dynamics Fatigue and fracture.

Janvier - Février - Mars.

PALAISEAU

G. Cote (ENSCP), A. Selmi (Orano), D. Viguier (Orano), A. Ndiaye (Orano), P. Guillermier (Framatome).

Cours ou TD en classe complète.

Presents the different types of nuclear fuels. Delivers scientific basis to understand the different steps of the front-end of the nuclear fuel cycle, from mining activities to fuel fabrication.

1-Introduction to nuclear reactors – EDF reactors
2-The nuclear fuels
-basic principles, required properties, criteria for design
-different kind of fuels (oxide fuels, metallic fuels, advanced fuels, etc.)
3-Uranium extraction and purification
-Uranium ressources, exploration and mining techniques
-Uranium ore processing
-Precipitation and flocculation in the uranium ore processing plants
-Interactive approach of Cominak process
-Data acquisition and hydrometallurgical plant design
-Remediation of uranium mines
4-Uranium conversion
-From uranium concentrate to uranium hexafluoride: the conversion
5-Uranium enrichment
- Main goals and basic principles
- Areva’s challenge on change management (from gaseous
diffusion to ultracentrifugation)
6-Fuel fabrication
-Pellets, pins, assemblies
-Oxide fuel fabrication processes
-Innovative fuels and innovative processes.

Solution chemistry.

Octobre - Novembre - Décembre - Janvier.

PARIS

P. Moisy, B. Dinh, M. Miguirditchian, S. Grandjean, G. Cote, G. Lefèvre.

Presents the main stakes of nuclear spent fuel recycling
Deliver the scientific basis of processing- recycling processes
Present current technologies and on-going R&D

1-The nuclear spent fuel (content, potential nocivity and energetic attractivity)

2-Spent fuel management options (recycling options, other options)

3-Uranium and plutonium recovery : principles and processes
-solvent extraction: basic principles, specificities of the nuclear field
-application to uranium/plutonium recycling

4-Minor actinides recovery
-possible drivers
-new extractants design (modern approaches)
-from molecules to processes

5 – From solvated recovered elements to solid compouds
- different kinds of processes (cristallization, others)
- poly-metallic compounds

6 – Recycling ("transmuting") actinides into reactors
- plutonium-bearing fuels
- MA-bearing fuels
- trends for future nuclear systems: possible strategies,on-going
research and emerging technologies.

Solution chemistry.

Novembre - Décembre - Janvier.

PARIS

FOUQUET Frédéric ZENG Zhiguo GROSSETETE Alain.

Half of the sessions are given in CentraleSupélec while the other half in INSTN. There will also be practical work on PWR simulator.

CentraleSupélec (21h)
Introduction – 3 hours
Modeling & optimization using linear programming – 3 hours
Modeling & optimization using non-linear programming – 3 hours
Modeling & optimization using genetic algorithm – 3 hours
Decision making techniques – 6 hours

INSTN (21h)
Part1 : Core operation – 6 hours (lecture given by a Framatome expert)
•Core control modes of PWRs
•Electric grid constraints; general principles of core control modes; design and functional requirements; A mode and G mode; the advanced T mode of EPR reactors; core related periodic tests.
Part2 : Reactor start up from reactor completely defueled to reactor in service, 100% stage – 15 hours (Lab work on SOFIA simulator)
•Pressure temperature buildup
•Start reactor coolant pump set
•Creation of steam bubble in the pressurizer
•RHRS disconnection
•Start-up constraint
•Reactor start up: approach to criticality and divergence (dilution, rod extraction, doubling time)
•Zero power physical tests: measurement of the moderator temperature coefficient, control rod worth, ?ISO
•Interactions between primary and secondary
•Configuration of the conventional island
•Power increase, connection of the turbine, power levels for physical tests, Xe effects.

Elementary knowledge of calculus, matrix theory, probability and statistics, PWR basic knowledge.

Lecture and reading materials from the lecturer.

Septembre - Octobre - Novembre - Décembre - Janvier.

Mathieu Arquier (STRAINS).

3 full days.

Objectives
The aim of this course is to give the students an overview on the actual dismantling operations through numerical modeling and calculations of deconstruction phases and hands-on training in order to address the different aspects of real-life dismantling operations (gowning, contamination non-propagation protocols, hard conditions operations, etc…)

Content
Training on a structural calculation program (Pythagore) used civil engineering. Basis of structural modeling and phasing of the different operations. Project : Modeling and deconstruction calculations of a concrete/steel structure in the presence of radiation. Calculation of the stability of the structure under the different design phases.
The students are to operate in dismantling situation : gowning, waste management, waste packaging, radiation control, good behaviors associated with various situations.
Enhanced Reality simulator session.

Thermodynamics Basics Continuum Mechanic Basics.

Janvier.

Ecole des Ponts (Champs sur Marne)

Sebastien Gervillers (ENPC).

5 x 3 lectures.

This course is the follow-up of Calculations Code 1 with a focus on Numerical Project.

Calculations Code 1.

Janvier - Février - Mars.

Ecole des Ponts ParisTech (Champs sur Marne)

Frédérique Damerval (Tech-y-tech) Eric Gouhier (CEA) Yvon Desnoyers (géovariances) Vincent Testard Jerome Ducos (CEA) Denis Giraud (ORANO) Magali Benchikhoune Fabrice Moggia.

1/Inventaire physique et déchet d'une INB ( méthodologie et moyens de caractérisation) 2/Scénarios de démantèlement – méthodologie 3/Methode geostatistique 4/Partie pratique : réalisation d'une cartographie géostatistique 2D d'une pollution radiologique avec le logiciel Kartotrak en salle informatique 5/OREKA DEM + optimisation des scénarios de démantèlement par la simulation 3D 6/Confinement et ventilation nucléaire 7/Techniques et procédés de décontamination 8/Désamiantage en milieu nucléaire 9/Decommissioning a fusion reactor : specificities, strategy and main related risks 10/Decommissioning and radioactive materials transportation risks, decommissioning and fire risks 11/Moyens : Scan 3D, autres - Illustrations 12/Etude de cas 13/Exam.

Objectives
The aim of this course is to apply the technical knowledge and regulations learned by the students during the first semester in the context of a dismantling project.
Students are given a case study and must analyze different scenarios in order to define a realistic set of solutions addressing the various aspects of the dismantling project.

Janvier - Février - Mars.

Ecole des Ponts ParisTech (Champs sur Marne)

Xavier VITART (CEA) Frédérique HOURCADE (Orano) Muriel FIRON (Orano).

All the lessons are performed by professionals ( ANDRA, CEA, ORANO, EDF, companies), deeply involved in Decommissioning and Waste Management projects or R&D activities in the field. The pedagogical methods ara funded on learning by problems and by projects, with a high level of implication of the students, through interactions with the teachers, and through projects studies in groups. Visits are organised in order to confrontate the students with the field realities.

The aim of this module is to give the students all the necessary tools, from physical, regulatory and, practical points of view, related to the management of wastes produced by the cleaning and the dismantling of nuclear facilities. The first lessons deals with the different categories of waste (short, medium and long lived, low,medium and high activities), the regulations ( french and international point of view), the role of ANDRA (french national agency for the final managing of radiaoactive waste), and the way to characterise the waste inside their different matrix (methodology, instrumentation, « reference spectra »). The second part deals with the practical way to manage the radiaoctive wastes and send them to ANDRA. Particular attention, through real cases studies, is given to the french concept of « waste zoning ».

Pre-requisite are the fundamentals of the engineering sciences (physics, chemical engineering, mechanical engineering), and a good knowledge of the fundamentals of radioactivity (from the nature of radioactivity emissions to basic principles of radioprotection).

- Policies and Strategies for the Decommissioning of Nuclear and Radiological Facilities IAEA Nuclear Energy Series NW-G-2.1 - Guide de l'ASN n°6 : Arrêt définitif, démantèlement et déclassement des installations nucléaires de base - Guide n°14 de l'ASN r.

Janvier - Février - Mars.

GIF-SUR-YVETTE

C. Sorel, D. Guillaumont, T. Dumas, B. Dinh, G. Kritchik, T. Vercouter, H. Isnard, S. Charton, H. Roussel, F. Lamadie, C. Rivier.

Cours et Cours/TD à Chimie ParisTech. TP au CEA Saclay et CEA Marcoule.

1. Introductory lecture to relate the significance of analytical and modeling tools within the current and future recycling processes.

2. Molecular modeling of actinide – ligands interactions: principles, tools, results, key challenges for actinides

3. Spectroscopic understanding of actinide environment: principles, tools, perspectives. Focus on EXAFS informations

4. Modelling and simulation of solvent extraction processes
Introduction to process simulation: principles and main methods, presentation of PAREX code and applicative tool (SIMULEX …)
5. Introduction to nuclear fuel cycle scenario: objectives, challenges and tools.
Focus on the dynamic fuel cycle simulation code COSI. Application to different fuel cycles: one-through, Pu recycling in PWR MOX, Pu multi-recycling in fast reactors. Analysis of the impact on scenario results including plutonium inventory and uranium consumption.
6. Modern analytical tools to characterize radionuclides speciation

7. Isotopic measurements in nuclear industry: analytical techniques and applications for nuclear fuel cycle.

8.Solvent extraction technology: Contactors Design & Modelling
9. On-line and off-line measurements for process monitoring.

Solution Chemistry.

Janvier - Février - Mars - Avril.

PARIS

B. Yven, B. Madé, C. Martin, G. Pépin, B. Cochepin.

The course is formed by four complementary parts: (1) an overview of the radioactive waste management issues, with their current solutions and prospective; (2) a focus on radionuclides behaviour in porous media, illustrated by practical applications; (3) a presentation of the multi-disciplinary approach to move, using numerical simulation, from phenomenological understanding to global performance and safety assessment; (4) science and society.
The course is completed by field visit of the French disposal facilities in operation for low- intermediate level short live waste (LIL SL), for very low level waste (VLL) and/or of the Underground Research Laboratory (URL) for high level and intermediate long lived waste disposal (HL/IL LL).
1.Overview on radioactive waste management issues
2.Radionuclides behaviour in geological repository conditions
3.From the phenomenological understanding to a repository safety analysis
4.Science and society: of national and territorial interest, Cigéo.
5.Field Visits : Disposal facilities for low- intermediate level short live waste (at Soulaines, Aube) and very low level waste (at Morvilliers, Aube) and Meuse and Haute-Marne Underground Research Laboratory, in which experiments are conducted on the feasibility of deep geological disposal of for high level and intermediate long lived waste (Bure, Meuse).

Janvier - Février - Mars - Avril.

PARIS

F. Bart, C. Roussel, O. Pinet, F. Frizon, F. Lemont, C. Ferry, D. Caurant, O. Majérus.

1.Introduction to present a general overview of the content of WAST Course : the general ideas and the presentation of the content of the modulus is given during the first hour and to work on real cases

2.Waste Management resulting from Nuclear Used Fuel : description of the main nuclear waste routes to treat and condition HLW and ILW explain to yield to a satisfactory wasteform

3.Nuclear Glasses : historical and scientific elements that led to the choice of glasses for nuclear high-level waste containment.

4.Cementitious matrices : historical and scientific elements that led to the choice of cementitious matrices for nuclear low and intermediate level waste containment

5.High Temperature Processes : presentation of the different processes used to treat high and intermediate level burnable liquid and solid waste.

6.Spent Fuel : physical and chemical properties of spent nuclear fuel after irradiation in reactor, and mechanisms of spent fuel evolution during the storage phase and under disposal conditions

7.Glass chemistry applied to nuclear waste containment : physical and chemical properties of multicomponent glasses as a function of their composition and long-term chemical durability of nuclear glasses.

Inorganic Chemistry.

Janvier - Février - Mars - Avril.

PARIS

Daniela Cancila.

Dependability of computer-based systems
The purpose of the lecture is to provide a theoretical and pragmatic knowledge of the dependability of computer-based systems. The way it impacts the architecture of computer-based systems as well as the design of their software will be described. The typical application is the computer-based Instrumentation & Control infrastructure of nuclear power plants: the history of stages and technical evolutions of French PWR I&C Design will be described as well as the structure of the control-command N4 I&C system (1450 MW) and the software aspects of the protection system.
Model-Checking is one major technique of automatic verification of computer-based control systems. It automatically checks and proves that a system, or a mathematical model of a system, validates some safety properties formalized within a temporal logic. Many case studies will be presented to students and many labs will be proposed.

Basic knowledge in software engineering and programming.

Janvier - Février.

PALAISEAU

Didier Schoevaerts, F Lignini, M Pfeiffer, P Videlaine, B Lenogue, M Vaindirlis, A Chabod, C Duval, B-J Willey, A Wasylyk, J Grosmaire.

CM: 39h

Session 1 : Mid Term examination (written or oral) (0,5) Final examination (Written or oral) (0,5)

Session 2 : Final examination (written or oral) (1).

Objectives:

-Explain the main general bases of the design of a nuclear power plant, the equipment and the systems, taking into account the nuclear safety requirements, the design codes and standards with their recent evolutions (regulatory and industrial context)
-Describe the architecture of the systems and the equipments of the nuclear installations and the associated instrumentation and control features
-Describe the rules for selecting of nuclear sites and their environment
-Describe the provisions taken in the design relative to radiation protection issues.

Janvier - Février - Mars.

PALAISEAU

Yves Crolet, Pierre-Alain Naze, Elie Petre-Lazar.

Janvier - Février - Mars.

PALAISEAU

Jean-Francois Semblat.

The organization of the various topics is described above. The course will alternate lectures with tutorials. Videos from a MOOC in the same field will also be used. The evaluation will be made through a seismic design project.

This course ranges from the science of earthquakes (seismology) to their effect on civil engineering structures (earthquake engineering). It is organized as follows:
1.Seismicity of the Earth and wave radiation by faults.
2.Seismic wave propagation: elastic waves and wave conversion.
3.Surface waves and seismic wave amplification: from theory to practice.
4.Soil dynamics and wave attenuation.
5.Dynamic soil-structure interaction.
6.Seismic response of structures: the response spectrum.
7.Seismic response of equipments.
8.Nonlinear seismic response of soils and structures.
9.Principles of seismic isolation.

Fundamentals of: •mechanics of solids and structures, •waves and vibrations. Basics in numerical methods.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Jean-Michel Torrenti, Adelaide Ferraille, Christophe Bernard, Benjamin Terrade.

6 courses (at ENSTA and Ifsttar) + 2 practical works (at Ifsttar).

1) Constructive principles of reinforced and prestressed concrete, example of the nuclear confinement vessels ·
2) Constitutive materials of concretes: cement, aggregates, water, admixtures, additions ·
3) Rheology of fresh concrete:
4) Mechanical behavior of the hardened concrete,
5) Delayed strains : shrinkage, creep
Practical Works 1: Manufacture of a concrete formulated during the course (compression sample + reinforced beam)
6) Durability of concrete
7) Modern concretes
8) Mechanical behavior and durability of steel in concrete structures
Practical Works 2: 28 days after part 1, compression and splitting tests on samples and loading of the beam in flexure.
2) les pre?-requis:.

Mechanics of material.

Septembre - Octobre - Novembre - Décembre.

PALAISEAU

Kevin Ogle.

Janvier - Février - Mars.

PALAISEAU

Ioannis Politopoulos, Emmanuel Jeanvoine.

CM: 6h, TD: 12h, Projet: 15h.

Master the fundamental aspects of the finite elements methods and practice it in the context of the design of structures. Learn the different numerical algorithms especially those used in non-linear analysis of structures. Be able to solve highly non linear coupled problem with a degree of precision difficult to reach by classical methods (This fact is fundamental for the nuclear domain).
The students will be trained to write system of partial derivative equations associated with an actual problem from the nuclear domain, solve it numerically using a powerful finite elements software.
Each lesson is divided as follows: first the theoretical aspects associated with the studied phenomena is recalled, second its numerical treatment is specified and finally somes examples, will be solved using the finite elements software « Cast3m 2000 » and interpret the obtained results.

Good level in applied mathematics (analysis, algebra, optimization) Basic knowledge in software engineering and programming Elasticity (3D, beams, plates and shells) Heat conduction Plasticity Linear dynamics Non-linear dynamics Fatigue and fracture.

Janvier - Février - Mars.

PALAISEAU

Eric ROYER, Patrick DUMAZ (CEA).

This 33-hour module consists of 20.5h of course, 3.5h of tutorials and 9h according to a « project » approach. . The project is based on the implementation of a nuclear thermal-hydraulics calculation code. The instructions, details regarding the code and the supervision of the student works needs the presence of students and experts together for 9h. In addition, each student has to lead his own investigations and calculation to treat the subject set by the teachers (computer room in free access).. A report is expected and constitute a component of the global mark related to this module. The knowledge assessment is completed by a written exm.

Advanced Thermal Hydraulics provides a deep knowledge of single- and two-phase flows encountered in nuclear reactors, particularly for design and safety studies.

- Advanced fluid mechanics: turbulence modeling (RANS, LES, introduction to DNS), introduction to CFD computer codes, benefits and limitations of these codes.

- Nuclear reactor design: introduction to gas coolant and liquid metal coolant, comparison with LWRs.

- Advanced two-phase flows: introduction to multi-scale modeling from DNS to porous media), equations systems for two-phase flows (from HEM to multi-fields), condensation with non-condensable gas, CHF prediction, two-phase flow instabilities (Ledinegg instability, density wave oscillations, BWR instabilities), critical mass flow rate (particularly for application to LOCAs).

- Thermal Hydraulics for severe accidents: hydrogen combustion, corium behavior (in- and ex-vessel phenomena).

The previous semester module « Thermal-Hydraulics » (S3-D-O-R-FLUI) is a convenient prerequisite.

N.E. Todreas, M.S. Kazimi, Nuclear systems I, Thermal Hydraulic Fundamentals, Taylor & Francis.

Janvier - Février - Mars.

GIF-SUR-YVETTE

Jean-Baptiste BLANCHARD, CEA Saclay Davide MANCUSI, CEA Saclay Cyril PATRICOT, CEA Saclay Andrea ZOIA, CEA Saclay.

The course is delivered successively by three teachers for the topics associated to multiphysics and those corresponding to uncertainty, respectively:

•Multiphysics (7.5h, Cyril PATRICOT): oCours : 4.5h oCours-TP : 3h •Uncertainty (4.5h, Jean-Baptiste BLANCHARD): oCours : 4.5h •Coupling with Monte Carlo (3h, Andrea ZOIA): oCours : 3h.

Initiation to the multiphysics approaches integrating mainly thermal-hydraulics, neutronics and thermal-mechanics:
•Generalities on reactor physics and analysis focused on multiphysics modeling problematics:
oSignificance, reasons and different steps of the modeling.
oWriting and analysis of a nuclear reactor simple multiphysics modeling.
oDiscussion on emergence of “best estimate” multiphysics modelings. Their novelty and link with the
safety approach.
•Provide to the student first skills on the multiphysics modeling through “Travaux pratiques” using a simplified
multiphysics code, THEDI.
oInvestigation of several phenomena: transients due to temperature variations, loss of flow, reactivity
insertion.
oIntroduction to basic fuel physics issues.
•Introduction to coupling numerical techniques.
oPresentation to some non-linear solving algorithms: fixed point (acceleration), Newton-Raphson
algorithm.
oConcepts of time scheme (explicit, implicit), order of convergence.
•Uncertainty problematics:
oMultivariate probability laws, covariance/correlation.
oUncertainty propagation techniques (Design of experiment, meta-modelling).
oSensitivity analysis.
•Specificities of the coupling with a Monte Carlo code illustrated on a Reactivity Injection Accidents :
oKinetic Monte-Carlo.
oImpact of the statistical noise.
oParallel simulations and performances.

Mathematics: Notions on differential equations, numerical analysis, linear algebra. Physics: Notions on thermal-hydraulics, neutronics, thermics.

Keyes, David E., et al. "Multiphysics simulations: Challenges and opportunities." The International Journal of High Performance Computing Applications 27.1 (2013): 4-83. Saltelli, A., et al. Global Sensitivity Analysis: The Primer. Wiley, New York, 2008. Sjenitzer, B. L., et al. "Coupling of dynamic Monte Carlo with thermal-hydraulic feedback." Annals of Nuclear Energy 76 (2015): 27-29.

Janvier - Février - Mars.

GIF-SUR-YVETTE

Stéphane BOURGANEL, Antoine COLLIN, Cheikh DIOP, Hervé GOLFIER, Alexis JINAPHANH, Yi-Kang LEE, Emiliano MASIELLO, Simone SANTANDREA (CEA Saclay), Eric DUMONTEIL (IRSN).

The course is organized according to the following architecture:

•Deterministic transport course part 1: 16,5h (Hervé GOLFIER) •Deterministic transport course part 2: 12h (Simone SANTANDREA) •Computational training on numerical methods: 4,5h (Emiliano MASIELLO) oPratical work using APOLLO2 neutronics code/study of physical effects: 9h (Antoine COLLIN)

•Practical work using TRIPOLI-4® Monte Carlo transport code: 6h (Cheikh DIOP) oGeneral presentation and primer use: 3h (Yi-Kang LEE, Stéphane BOURGANEL) ; oFixed source problem/radiations strong attenuation: 6h (Yi-Kang LEE, Stéphane BOURGANEL) oEigenvalue problem/core physics-Criticality studies: 6h (Éric DUMONTEIL, Alexis JINAPHANH)

The module is evaluated through exams related to the different courses and through practical work reports related to APOLLO2 and TRIPOLI-4® codes.

The general aim of this module is:
•To understand the notion of “calculation schemes” and its validation devoted to industrial and
R&D applications .
•To acquire knowledge of the mathematical and the physical foundations of the nuclear core modellings.
•To acquire neutronics calculations basic skills through specific practical works using simulation softwares.
The course is focused on the three main aspects of neutronics calculations:
•The different approaches used to carry out nuclear core calculations. For this aim the topics dealt with are
the following:
oAn overview of neutronics calculation schemes - reference/deterministic/Monte-Carlo.
oThe study of the fundamental mode, BN and PN Boltzmann equation treatment.
oThe core calculation scheme based on diffusion approximation and SPN method.
oThe validation and qualification methodology applied to the neutronics calculations.
•Two major deterministic numerical methods developed to solve the Boltzmann equation :
oThe Collision Probability Method (Pij);
oThe Method of Characteristics (MOC)
• The probabilistic Monte Carlo method that is able to carry out :
?a core calculation “exactly” in 3D geometries.
?a strong attenuation flux in radiation shielding 3D configurations.
The advantages and the shortcomings of the previous approaches are discussed. The convergence problematics of these computational methods addressed as well.

Mathematics: differential equations, linear algebra, linear operators, probability, statistics. Neutronics 1 content course.

Paul Reuss, Neutron Physics, Les Ulis, INSTN/EDPSciences, 2008. J. J. Duderstadt, L. J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons, 1976. Alain Hébert, Applied Reactor Physics, Montréal, Presses internationales Polytechnique, 2009. T. J. Akai, “Applied Numerical Methods for Engineers”, 1994, J. Wiley & Sons Inc. llya M. Sobol, A Primer for the Monte Carlo Method, London, CRC Press, 1994. J. Spanier and E. M. Gelbard, Monte-Carlo Principles and Neutron Transport Problems, USA, Addison-Wesley Publishing Company, 1969. Neutronics, A Nuclear Energy Division Monograph, ouvrage collectif

Janvier - Février - Mars.

GIF-SUR-YVETTE

Louis -Joseph BONNAUD, Frédéric FOUQUET, Hubert GRARD (CEA/INSTN).

The course is composed of both “Course-Tutorial” and “Course-Practical Work” for each following items:

Applied neutronics: oTemperature effects: 3h oKinetics describing transient situations: 3h oPoisons (xenon and samarium) and xenon oscillation: 3h. oCoupling between primary and secondary circuits which involved both the steam flow and the reactivity: 3h. oPractical implementation via a 3D virtual reality device (fuel loading operation for instance): (“Practical Work”): 3h.

Applied system thermalhydraulics: oStart-up of a PWR: 3h oThermosiphon system behavior: 3h oPrimary circuit accident: small, intermediate, large pipe breaks: 3h oSecondary circuit accidents: (link with the "Applied neutronics" part with respect to the thermalhydraulics/neutronics coupling): 3h.

The objective is to study the practical aspects of reactor control and operation. The module is divided in two main parts:
•The applied neutronics which concerns mainly the reactivity effects:
oTemperature effects.
oKinetics describing transient situations.
oPoisons (xenon and samarium) and xenon oscillation
oCoupling between primary and secondary circuits which involved both the steam flow and the reactivity.
oPractical implementation via a 3D virtual reality device (fuel loading operation for
instance).

•The applied system thermalhydraulics considering both the PWR normal operation and accidental situations using a sophisticated simulator based on the CATHARE code. The aim is to be able to describe the thermo-hydraulic behavior of the primary circuit in normal and accidental operation and to decompose the main stages of the start of a PWR on the one hand, and accidents studied on the other hand.
oStart-up of a PWR.
oThermosiphon system behavior.
oPrimary circuit accident: small, intermediate, large pipe breaks.
oSecondary circuit accidents:
?steam line break: accidental transient stud with a strong thermalhydraulics /neutronics coupling)
?Hydrogen scenario.

Basics knowledge acquired in nuclear physics (beta-neutron decay, precursors properties…), Neutronics 1, Thermalhydraulics, PWR Functional Description, Introduction to Safety.

Paul Reuss, Neutron Physics, Les Ulis, INSTN/EDPSciences, 2008. J. J. Duderstadt, L. J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons, 1976. N.E. Todreas, M.S. Kazimi, Nuclear systems I, Thermal Hydraulic Fundamentals, Taylor&Francis.

Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Zeng Zhiguo, Fang Yiping.

IndexContentHours 1Maintenance: basic concepts3 2Corrective maintenance: modelling, analysis and optimization (I)3 3Corrective maintenance: modelling, analysis and optimization (II)3 4Scheduled maintenance: Age-based and block replacement (I)3 5Scheduled maintenance: Age-based and block replacement (II)3 6Condition-based and predictive maintenance through PHM (I)3 7Condition-based and predictive maintenance through PHM (II)3 8Condition-based and predictive maintenance through PHM (III)3 9Resilience modelling and optimization3 10Review and exercise3

The course will be given at CentraleSupélec. There is no written examination for this course. Grading will be based on a course project.

Course Descriptions:
Maintenance is important in engineering systems. In this course, we focus on the optimal planning of maintenance for complex systems. Different maintenance strategies are introduced with a focus on the performance indicators used to quantify their performances and optimization models used to obtain optimal planning. The students are supposed to learn fundamental theoretical results as well as some tools to help them apply the theoretical methods in practical.

Objectives:
In this course, we focus on maintenance planning for industrial components and systems. The objectives of this course are:
?to understand basic concepts in maintenance and fundamental models and methods for maintenance planning;
* to understand important concepts and methods for prognostics and health management, and their application on maintenance planning;
* to grasp how to use computer tools and software (e.g., Matlab) to help implement the theoretical methods in practice;
* to understand how to apply the theoretical methods to support maintenance management of nuclear power plants in practice, through real-world examples from industry.

Elementary knowledge of reliability engineering, calculus, matrix theory, probability and statistics.

Lecture and reading materials from the lecturer. · Zio E. An introduction to the basics of reliability and risk analysis. World scientific; 2007. · Rausand M, Arnljot Høyland. System reliability theory: models, statistical methods, and applications. John Wiley & Sons; 2004.

Janvier - Février - Mars.

GIF-SUR-YVETTE

DEBES Michel, PAUTROT Patrice, HOROWITZ Emmanuel, MARQUIS Bruno.

The course will be given at CentraleSupélec.

Objectives:
- To get acquainted with the main aspects of safety during day to day operation of NPP, safety standards and codes, regulatory framework, the fundamentals and key points of the safety approach and issues regarding implementation of Safety culture and Defence in Depth in normal operation, technical specifications and testings, incident and accident procedures, severe accident management and emergency planning, long term operation and periodic safety reassessment, experience feedback and event analysis: root causes and potential consequences;
- To develop its own assessment and awareness of the importance to safety of facts and technical issues related to NPP operation and ability to implement Defence in Depth regarding prevention, surveillance and means of action in the control of day to day operation and maintenance activities, taking into account human factors, quality approach, risk analysis and potential consequences;
- To understand the overall international experience and safety standards which are at the basis of the structure and evolution of safety approach worlwide, taking into account illustrative safety cases.

Contents:
- Nuclear Safety in Operation
- safety standards and regulatory framework
- Nuclear operation in load following
- Basic Knowledge of Severe Accidents
- International experience feedback regarding major incidents and accidents and events
- RCCM and RSEM codes for pressure vessel design and monitoring,
- Fuel operation.

General knowledge in neutronics, thermal-hydraulic, mechanics.

IAEA standards; nuclear physics; nuclear accidents.

Janvier - Février - Mars.

GIF-SUR-YVETTE

CANCILA Daniela CAMMI Antonio CALMON Pierre.

The course will be given at CentraleSupélec.

The course starts with a General Introduction; History of stages and technical evolution of French PWR I&C Design; Structure of the control-command N4 I&C system (1450 MW); and Software Aspects of the protection system. Two lessons are devoted to OASIS technologies and an OASIS-based Qualified Display System for TXS platform. Finally, the course addresses the Nuclear Accidents (TMI-2, Chernobyl, Fukushima) under the social impact umbrella. A brief discussion on the technical details and the safety regulation (IEC 60880, IEC 62138, IEC 61513) is provided.
The second part directly addresses simulation. An introduction to nuclear computational science. Overview on different codes used in nuclear industry. Platforms and simulation tools.. Introduction to hydraulic components modeling. Numerical simulation techniques. Monte Carlo codes and simulation. An Introduction to multi-physics simulation. Introduction to OpenFOAM software as a multi-physics solver.
In the third part on ultrasonic non-destructive testing (NDT), the importance of NDT and its advantages are first given, followed by modeling issues of NDT simulations. The physical aspects of the ultrasound used for NDT are described, which lays the basis to understand the echoes due to defects.

Janvier - Février - Mars.

GIF-SUR-YVETTE

Frédéric FOUQUET (CEA/INSTN) Grégory CAPLIN (Orano) Mathieu MILIN (IRSN).

Because it is a prerequisite for the “Criticality-Safety” course the “Introduction to Safety” course is the first to be taught in the module.

The 12-hour “Introduction to Safety” part consists of a 11-hour “course” part and a 1-hour “course-tutorial” part each addressed to the full-class. The 12-hour “Criticality-Safety” part consists of a 6-hour “course” part addressed to the full-class, a 3-hour “course-tutorial” part addressed to the half-class (two student groups), and a 3-hour “tutorial” part addressed to the half-class . Such modalities strength the interaction students/teachers and make the learning more effective.

The all nuclear activity sectors are interested by the operationnal problematics of the Safety and Criticality-Safety treated.
1.Introduction to Safety

Introduction
•Deterministic approa
•Safety barriers and functions
•Accident classification
•Design Basic Accident
•Safety culture, organization & quality
•Practical example : Study of a Loss Of Coolant Accident

Operation and Safety
•International standards
•General Operating Rules, Operating Technical Specifications,
•Emergency procedure
•Periodic safety review
•Maintenance management

Probabilistic safety assessment
•Probabilistic Risk Assessment
•Safety goals
•Event/fault tree
•Strengths & limitations

Emergency preparedness
•Crisis organization in France
•Emergency preparedness response
•On-site emergency plans / off-site emergency plans
•Dispersion model

Enhancing safety
•Beyond Design Basic Accident
•Internal & external hazards
•TMI, Tchernobyl, Fukushima scenarios
•Post-Fukushima action plan
•Experience feedback for the EPR

2. Criticality-Safety

- To understand the consequences and the phenomenology of an inadvertent criticality in a fuel cycle facility (except operating nuclear cores) or during a transport of fissile materials,
- To know how to prevent the occurrence a criticality accident (methods of control, double contingency principle, safety assessment, calculation methods and hypotheses, margins of subcriticality…) and how to limit the consequences of such an accident, should it occurs.

Prerequisites for « Introduction to Safety »: Basic knowledge on PWR (components, systems and operation).

Prerequisites for « Criticality-Safety »: Basics Neutronics. « Introduction to Safety » course is also a prerequisite.

1. “Introduction to Safety” part:

IAEA website : « safety of nuclear power plants » documents •https://www.iaea.org/search/google/safety%20of%20nuclear%20power%20plants •https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/3mile-isle.html

2.“Criticality-Safety” part:

* T.P. McLaughlin et Al., “A Review of Criticality Accidents”, 2000 Revision, LA-13638,

* “Analysis Guide – Nuclear Criticality Risks and their prevention in plants and laboratories”, DSU/SEC/T/2010-334, http://www.irsn.fr/EN/publications/technical-publications/Documents/IRSN_report_nuclear_criticality_risks.pdf.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Philippe MASSIOT (INSTN) François TROMPIER, Estelle Davesne (IRSN) Cheikh DIOP (CEA Saclay) Nathalie DRAY (Framatome).

This module consists of 28.5h/student. The teaching implements a wide range of pedagogical methods including labs, calculation codes and serious games, a training pilot facility. According to the pedagogical method used the class has to be divided into two 25-student groups or four 12-student groups.

Complete knowledge and operational skills in Radiation Protection are provided by implementing a wide range of approaches.

1. Using the international regulation frame of reference
- Identify the actor of international and national regulation (ICRP, IAEA, EU, ASN ...)
- Describe the radiation protection principles

2. Describe the main uses of radiation in various fields
- Categorize and explain the different types of radiation sources (natural and industrial).

3. Apply the three means of protection against ionizing radiation
- Apply radiation protection by reducing the exposed time, by setting up shielding, by increasing the distance.
- Determine the collective and personal protective equipment.

4. Characterize a workplace study:
-Apply and supervise workplace study.

5. Describe the external dosimetry concepts:
- Differentiate the efficiency of different shielding for different radiation.
- Calculate shielding manually and by using calculation code.

6. Apply the external dosimetric concepts:
- Assess and interpret external dosimetry.
- Apply the different operational and protection quantities used for dosimetry.
- Apply deterministic and/or Monte-Carlo method to resolve transport equation.

7. Explain the principles of internal dosimetry:
- Describe the physical aerosol aspects and kinetic biological models.

8. Identify the biological effects of ionizing radiation:

9. Use different detection devices:

10. Study the accidental / incidental situations:.

Nuclear physics: radioactivity, emission intensity, directly and indirectly ionizing particles, beta particles, x-rays, gamma-rays, cross sections of interaction. - Interaction of radiation with matter: • Interaction of photon with matter: •Interaction of light and heavy charge particles with matter •Interaction of neutrons with matter: elastic and inelastic scattering, capture, fission, transmission law.

- Introduction to radiological physics and radiation dosimetry, F. H. Attix, Wiley, 1986. - ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. Oxford: Elsevier; ICRP Publication 103; 2007. - Knoll, G. F. Radi.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE

Gilles MATHONNIERE (CEA Saclay). A compléter.

This 15-hour module is divided into five three-hour slots. Each slot is devoted to one part of the course.

The educational objective of this teaching module is to raise student’s awareness to the flexibility aspects which will have an increasingly influential role especially for electricity. The complementarity of variable renewable energy sources (VRE) and nuclear will be addressed both technically and economically.
This teaching module is divided into 5 parts:
•The global energy situation. Trends will be highlighted: slowing down the use of fossil energy and a fast increase in electricity demand. As this electricity has to be as decarbonated as possible, the electricity mix will rely mainly on VRE, hydraulics and nuclear.

•The power electric grid, flexibility, the future role of nuclear power. Presentation of the electrical network and its various constraints to function properly. Presentation and discussion on the future decarbonated electrical mix, the flexibility of nuclear power will play a leading role. Some ways of improvement for the future will also be mentioned (SMR, PWR without boron, Fast reactors).

•Economic aspects. The consequences from an economic point of view are analyzed.

•The cogeneration. Presentation of the heat market, heat distribution networks, the potential of nuclear reactors in this field and some feedback from projects carried out abroad.

•Hydrogen production. Presentation of the hydrogen market, the cost of hydrogen production by electrolysis and the possibility of finding a business model for a nuclear reactor based on both the production of electricity and hydrogen.

No specific prerequisite. Interest for both economy and electricity supply is desirable.

•The costs of Decarbonisation : System Costs with High Shares of Nuclear and Renewables OECD/NEA •Projected Costs of Electricity Generation IEA/NEA •Cany, C., Mansilla, C., Mathonnière, G., & da Costa, P. (2018a). Nuclear contribution to the penetration of variable renewable energy sources in a French decarbonised power mix. Energy, 150, 544–555. •Leurent, M., Jasserand, F., Locatelli, G., Palm, J., Rämä, M., & Trianni, A. (2017). Driving forces and obstacles to nuclear cogeneration in Europe: Lessons learnt from Finland. Energy Policy, 107, 138–150. •Tlili, O., Cany, C

Janvier - Février - Mars.

GIF-SUR-YVETTE

Pascal DANNUS (CEA.INSTN) Frédéric DAMIAN, Richard LENAIN, Jean-Baptiste THOMAS (CEA/DEN).

1.Nuclear Fuel Cycles part: The 6h of “course-tutorial” (“cours-TD” in French) slots will be delivered by two teachers together in front of the full class. The 3h of tutorial (“TD” in French) will be addressed 2 half-class (2 groups of students) in parallel. 2.Nuclear Reactor Systems part: 18 h of “course-tutorial” will be delivered at a time. Three teachers are successively involved with the following distribution: a.Introduction, Gen-IV, Design and Prospects (J.B. Thomas) b.Gen-IV HTR, Gen-I reactors (including Gas-cooled reactors, heavy water reactors and RBMK), Experimental Reactors (R. Lenain) c.Gen-III including BWR, Innovation and Multi-recycling, toward Gen-IV nuclear fleet (F. Damian).

1.Nuclear Fuel Cycles :
•To highlight the strong links between the LWR features and its fuel in order to determine the right front-end
steps needed to produce the convenient fuel as well as its amount.
•To underline the costs related to each front-end step and to identify the leeway to reduce them.
•To identify the disposal ways regarding to the category of nuclear waste.
•To compare the “once-through” and the “reprocessing-recycling” back-end options by taking into account the
capacities to save uranium resources, the capacities to reduce the volume and the radiotoxicity of nuclear
waste.

2.Nuclear Reactor Systems
• To provide a general vision of the main nuclear reactor designs and systems, including the Small Modular Reactors (SMR) and Molten Salt Reactors (MSR)
•From the descriptive and historical knowledge of the nuclear reactor systems, identifying the strengths & weaknesses of designs dedicated to specific priorities.
•From the dynamic analysis of the last decades (depending on the forces acting within the energy field): identify the main drivers leading to the present situation and trends.
•Combining critical constraints (safety, competitiveness, proliferation resistance, rise of intermittent power sources) with mean term requirements (resources and waste management) in order to become able to contribute proposing relevant fuel cycle and reactor development options and schedule.

Basics of U chemistry. Basics of Radiation Protection. PWR functional description. Basics of system thermodynamics, of neutronics, thermal hydraulics, fuel cycle.

“Treatment and recycling of spent nuclear fuel; actinide partitioning – Application to waste management”, Monographie CEA/DEN, Editions Le Moniteur, 2008 “Nuclear Reactor Systems”, collection Génie Atomique, EDP Sciences (2016) Several books from Monographie CEA/DEN, Editions Le Moniteur, each of them dedicated to a specific system.

Novembre - Décembre.

GIF-SUR-YVETTE

Louis-Joseph BONNAUD (CEA/INSTN) Experts EDF, Framatome.

This 24-hour module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

It consists of 21h of courses addressed to the full-class and 3h of tutorial addressed to half-class (two groups). After following the teachings of the module, students will be able to describe the general organization of PWR in the context of a normal operation including: -the functional role of the components of the nuclear island as well as the main physical phenomena associated; -nuclear auxiliary fluid systems; -the conventional island. They will have assimilated the economic issues related to the thermodynamic performance of water-steam conversion cycle, security and economic issues related to the fuel and its management. The concepts of Burn Up, hotspot factor, loading pattern associated with safety criteria are thoroughly described.

This module describes the power reactors. It focuses on PWR widely used in the world, on which the French nuclear industry has a good feedback. The courses provide skills and reinforce the student’s interest whatever its specialization in the nuclear field.

-Architecture and components
•The1300 MWe PWR and function of each component of the RCS, including the vessel, the core, the fuel assemblies, the RCCA, the pumps, the pressurizer, the steam generator, the containment building and the nuclear auxiliary building
•The different stages of refueling and identify the spent fuel pool, the storage racks, the fuel transfer device, the refueling cavity…
-Main auxiliary systems
•Chemical and volume control system, reactor boron and water makeup system, residual heat removal system, spent fuel pit cooling and treatment system
•Main function performed, the basic flow diagram and the operation of these systems
-The nuclear fuel
•Market and stakes of the nuclear fuel
•The fuel assembly
•Cladding integrity, its reliability and the feedback on it
•Reactivity control including control rods, soluble boron and burnable poisons
•The core-loading pattern with goal and stakes
-Thermodynamic cycle: design and performance
•Thermodynamic cycle of a PWR and and the different ways to improve the energy efficiency
•Thermodynamic cycle and the industrial tools allowing to calculate it.

General physics, thermodynamics, fluid mechanism and heat transfert.

Barré, B. et al. (2016). Nuclear Reactor Systems. Edp Sciences. Reuss, Paul (2008). Neutron physics. Edp Sciences.

Septembre - Octobre - Novembre - Décembre.

GIF-SUR-YVETTE