ANL\ Nuclear Engineering Division\ IAEA Programs\ Training Courses

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.

Expected Output(s)

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.

Background Information

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.

Participants' Qualifications

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".

Course Calendar

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Social Calendar

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Course Materials

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

Course Evaluation

Course Photo

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