A Polish-French Initiative of Teacher’s training in Nuclear Engineering

1. A Polish-French Initiative of Teacher’s training in Nuclear Engineering Tomasz NOWACKI Ministry of Economy Poland Claude GUET Commissariat à l’Energie Atomique France

2. CONTEXT • A New Energy Policy : On January 13 2009, the following resolution has been adopted by the Government of the Republic of Poland : to ensure the national energy security, and taking into account the economic development, a Polish nuclear power program shall be developed and implemented. Towards first NPP’s in 2020 • Build up the human ressources Poland is convinced of the necessity to build and secure an appropriate skills environment to ensure a safe and efficient implementation of its nuclear programme. • A solid scientific and technological background

3. 20 professors from universities of technology Poland has selected 20 highly motivated university professors to become the cornerstone of the Polish nuclear educational system. These experienced professors have expertise in several technical or scientific domains relevant to nuclear technologies and France has been asked to propose a training offer ensuring that the selected professors acquire the necessary skills through a tailored programme in a limited time frame.

5. To answer the Polish requirement, France, under the coordination of the French International Nuclear Agency (AFNI) has prepared a training offer ensuring dedicated training with maximum interactivity with French stakeholders. Research & educational communities, safety authorities, industry members and operators are all involved in this offer. The proposed training path is structured in two main phases covering the October 2009 to June 2010 period.

6. Cooperation between France and Poland. • Partnership between all French nuclear energy stakeholders. • Phase 1. A six weeks nuclear Tour de France • To get well acquainted with a broad nuclear context • To visit Technical sites: NPP, fuel cycle, waste • To meet and exchange with French education network • To learn and exchange about communication and public acceptance • Phase 2. twelve weeks intense advanced training • Fundamental nuclear science • Applied courses (safety, radioprotection, NPP’s, waste,… • Access to experimental facities: ISIS, irradiation and characterization • Access to simulators • Focus on pedagogical issues

7. Phase I. Nuclear Introductory « Tour » Tihange La Hague Flamanville Caen Paris Fontenay Saclay Soulaines d’Huis Saint Marcel Châlon sur Saône Cluny Pierrelatte Romans Pierrelatte Cruas Bagnols / Ceze Marcoule Cadarache Aix en Provence

10. Phase 2: Nuclear Engineering Course organised by CEA-INSTNApril –July 2010

11. First Module: Fundamental Courses • Introductory nuclear physics – 1 week • Neutron Physics for Light Water Reactors (basics and advanced) – 2 weeks • Thermal Hydraulics (basics and advanced) – 2 weeks • Nuclear Materials – 40 hours • Computer codes – Modelling in Neutron Physics and Thermal Hydraulics – 1 week

12. Second Module: Applied Courses • Radiation Protection and Shielding – 1 week • Nuclear Fuel Cycle and Waste management – 1 week • Safety – Criticality - 1 week • Pressurized Water Reactors (PWR) – Functional description and operation - 1 week • Nuclear reactors systems – 24 hours

13. 2 -Neutron Physics for Light Water Reactors 60 hours, (36 hours courses, 12 hours lab sessions, 12 hours exercise sessions) ISIS Training reactor (6h):Approach to criticality, reactor start-up, divergence, doubling time, delayed neutron influence, reactivity control SIREP Simulator (3h):PWR start-up, approach to criticality, reactivity control, load Follow. Different temperature and poisoning effects during start-up and operation, PC simulators (3h):Point reactor kinetics equations, resolution, one or two groups model of precursors

14. Modelling Neutron Physics & Thermal Hydraulics • Duration: 1 week • Computer codes used to analyze physical phenomena. • Realistic studies carried out by computation. • Apollo2 (lattice physics deterministic code), • Tripoli4 (Monte Carlo code calculation), • Cathare ( TH system code), • Flica4 (core TH). • mini-project (4 days) with sensitivity studies and interaction between the different codes.

15. Radiation Protection and Shielding • 30 hours – 24 h conferences and 6 h exercise sessions • Course contents: • Fundamental physics behind radiological health engineering • Radiation units and monitoring methods • Shielding principles and calculations Exercise sessions: (6 hours) • shielding by anisotropic medium: line cylindrical and disc sources • multilayered shields • shielding of gamma rays sources, calculation of source strength, attenuation calculations • heating in shields: by neutrons, by gamma rays.

16. Nuclear Fuel Cycle for LWR – Waste Mangement • 30 h, 15 h courses, 6 h exercices, 9 h conferences • Course contents: • Main features of uranium • Front-end: Mining, Milling, Conversion, Enrichment steps • Fuel fabrication • Back-end: criteria for different options – spent fuel treatement – End products elaboration FP vitrification Lectures: • French experience in spent fuel & HLW interim storage technologies (AREVA). • R&D in the field of the long-live nuclear waste management: the transmutation (CEA)

17. Safety & Criticality • 30 hours courses and conferences • Safety • Overall safety approach – Historical perpectives – Current international context • Risk analysis – deterministic methods – probabilistic approach – human factor consideration • Safety design – internal/external hazards • Severe accidents Criticality • Tokaï Mura accident – Criticality calculation methods – storage of fissile materials in solution – heterogeneous fissile materials – transport of fissile materials

18. PWR functional description and operation • 24 hours courses + 6 hours on PWR simulator • Course contents • Technical and functional description of PWR reactors – Main auxiliary and safety systems – particularities of the EPR • Efficiency of boration and dilution – burnable poisons – influence of Xe over control – fuel evolution – residual heat – radiation sources • Normal power operation – free dynamics – priority to turbine – respect of the average coolant temperature set point « A » operating mode – specificities of other reactor operating modes On Sirep Simulator • Reactor free dynamics: study of  Priority to turbine, reactor follower • « A » operating mode : the principles. Bringing under control the axial flux distribution

19. Nuclear Reactors Systems • 24 hours - 8 lessons of 3 hours • Gas Reactors Magnox/UNGG ; AGR, • Heavy Water Reactors CANDU ; SGHWR ; EL4 • Reactors for nuclear-powered propulsion • Light Water Reactors PWR ; VVER ; BWR…. • Liquid metal cooled fast neutron reactors, • Recent projects under development (ABWR ; SBWR; AP600; S80+ ; EPR • Experimental reactors • High Temperature Reactors, Molten salts reactors, • Projects for the future ADS ; Fusion reactors ; ….. • Round table discussions