Training Course on the Safety Assessment of NPPs to Assist Decision Making
International Atomic Energy Agency (IAEA) and the Argonne National Laboratory (ANL), USA
Argonne, Illinois, USA
15 - 26 October 2012
The training course on "Safety Assessment of Nuclear Power Plants to Assist Decision Making" is intended to provide the general professional knowledge necessary for the participant to conduct safety assessment of new or operating nuclear power plants. Emphasis is placed on the basic concepts of safety including defence-in-depth and safety margins, and an overview of safety analysis methods, including deterministic and probabilistic analysis techniques, as well as their integrated use. The course is not intended to provide detailed instruction in performance of safety analysis or use of particular computer codes in safety analysis. The course should also meet needs of people having responsibility for management or leadership in performance of safety assessments, or people about to assume such roles, for an understanding of the concepts and methods used in safety assessment.
Knowledge transferred from experts to participants and shared among participants on the subject of the course.
Scope and Nature
The course is divided into 3 major topics: (1) Basic Concepts; (2) Deterministic Safety Assessment; (3) Probabilistic Safety Assessment
Each topic will be addressed through lectures, discussions between participants and lecturers, case studies, and practical exercises as appropriate. The course is intended to be participatory in nature, with continuous interaction between organizers, lecturers, and participants.
The overall objective of this project is to enhance and maintain high levels of nuclear safety in Member States by strengthening their capabilities for performing safety assessments of their Nuclear Power Plants. This Training Course will contribute towards this objective by providing and exchanging information on specific aspects as outlined above under the "Purpose".
The training course is open to 20 participants.
The target countries are: Armenia, Belarus, Bulgaria, Croatia, Czech Republic, Hungary, Kazakhstan, Lithuania, Poland, Montenegro, Romania, Russian Federation, Serbia, Slovakia, Slovenia, Turkey, Ukraine and Uzbekistan.
The course participants are expected to be professionals currently employed by utilities operating nuclear power plants, plant operating organizations, technical support organizations, or regulatory bodies. In general, they will be younger people, currently members of a safety assessment or safety analysis group.
The participant is expected to have basic knowledge of nuclear safety, such as that provided by the IAEA's "Basic Professional Training Course in Nuclear Safety".
The information will be available soon.
Please check back.
These files are password protected. The password will be given during the class.
- IAEA Fundamentals of Plant Systems.pdf
- Lecture 1.pdf
- Lecture 2.pdf
- Lecture 3.pdf
- Lecture 4.pdf
- Lecture 5.pdf
- Discovery of Fission and CP-1.pdf
- DSA and PSA in Decision-Making Process 2012 Vsn.pdf
- ENER554 Module 03 Safety, Licensing, Regulation.pdf
- INPO report on lessons learned from Fukshima Presentation.pdf
- Safety Culture in an Operating Organization.pdf
- VSN of DSA and PSA.pdf
- L1-Computer Models for Safety Analyses.pdf
- L2-User Effects.pdf
- L3-Plant modification.pdf
- Applications of PSA in Regulation.pdf
- DSA in New US NPPs.pdf
- Event Classification.pdf
- Impact of Fukushima.pdf
- Exercises for Introducing Probabilistic Safety Assessment Part 1.pdf
- Exercises for Introducing Probabilistic Safety Assessment Part 2.pdf
- L.3.2.7-8 Fire and Flood Risk Assessments.pdf
- L.3.2.9 External Events Risk Analyses.pdf
- L.3.3 Level 3 PSA.pdf
- L.3.3.A LEVEL 2 PSA.pdf
- L.3.3.B Relationship Between Level 1-2 PSA.pdf
- L.3.3.C Overview of Severe Accident Codes in US.pdf
- Introduction to PSA.pdf
- Accident sequence modelling.pdf
- Analysis of L1 PSA results.pdf
- System analysis.pdf
- NR 12C-- Examples.pdf
- R 12C-- Examples.pdf
- PSA at Exelon.pdf
- L3.2.12 PSA Software Overview.pdf
- L3.7 PSA in the IAEA Safety Publications.pdf
- Risk Informed Decision Making in Nuclear Industry.pdf
- Materials used in the reactor vessel head (look at Fig. 1b)Davis-Besse Reactor Pressure Vessel Head Degradation
- L3.2 Level 1 PSA - Overview.pdf
- L3.2.1 IE Analysis.pdf
- L3.2.3 Data analysis.pdf
- L3.2.4 CCF analysis.pdf
- L3.2.10 LPSD PSA.pdf
- L3.5 IRiDM.pdf