PLANNING 2012

June 11 to July 6  - Garching near Munich, Germany.

Attendance

This course teaches the technical and cultural bases of nuclear safety, nuclear security and radiation protection. These bases are necessary to work later as general safety practitioners in a regulatory body or to become safety/security specialist within a technical safety organization or the nuclear industry

Instructional Methods

Lectures, case studies and working group exercises are used. Technical visits are guided by TSO experts.

Program	Days
Fundamental of PWR technology-reactor core and fuel Basics of nuclear reactors safety; neutronics and core physics (criticality, neutron diffusion); thermal hydraulics and mechanisms of heat transfer; principles of core design and reactor core safety under operation.	1.5
Nuclear safety and radiation protection principles Radiation protection and nuclear safety principles (responsibility, leadership, justification, optimization defence in depth, control, limiting and protection systems and surveillance features); the global nuclear safety regime – EURATOM - national safety infrastructure.	0.5
Fundamental of reactor technology-circuits        Description of PWR main circuit, containment and main safety systems; NPP operation and control under normal and accidental situation; safety culture and management system; safety features of BWR technology; safety features of research reactors.	2.0
PWR materials and components management Thermal and mechanical properties of nuclear fuel and behaviour of fuel components under irradiation; QA in design, qualification, reliability; ageing management, degradation mechanisms, non-destructive examination	1.0
Nuclear security and non-proliferation Security principles and security culture; complementarity of safety and security; non-proliferation issues and international safeguards; physical protection, control of nuclear materials.	2.0
Application of safety and radiation protection principles Safety assessment methods and examples, periodic safety review; human factor issues in nuclear; radiation protection in nuclear facilities.	3.0
Accidents and nuclear events analysis Design basis accidents for PWR, BWR; internal and external hazards; severe accidents phenomena and simulation tools, probabilistic safety assessment.	1.0
Design and safety options of new generation of reactors Gen II, Gen III, III+, Gen IV evolutions; EPR, APWR, AP, ABWR, ESBWR, VVER; design options for Gen IV; R&D priorities including use of research reactors	2.0
Nuclear fuel cycle Fuel cycle general features; safety of fuel cycle facilities; fuel transport and storage; radioactive waste management; safety of decommissioning; safety of radioactive waste disposal	2.0
Radiation protection of people and environment and emergency preparedness Radiological impact assessment and surveillance of routine releases; radiological impact assessment of accidental releases; emergency preparedness; stakeholder involvement	2.0
Technical visits: Nuclear Power Plant – Nuclear Fuel Cycle facility – Research Reactor	3.0

Successful Completion of Program

This course program include working groups, simulator sessions, technical visits and open discussions.
Participants sign in every day. A technical evaluation will be performed on the full course content.
A certificate issued at the end of the training  period certify the acquisition of knowledge.

Registration fee

This course registration fee is € 10.800. Fee covers attendance at all sessions, full course documentation, technical visit as well as lunches, refreshements and coffee breaks.