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Argonne\ Nuclear Engineering Division\ IAEA Programs\ Training Courses

Training Course on the Safety Assessment of NPPs to Assist Decision Making

14 – 25 October 2013


PROSPECTUS

Purpose

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 information will be available soon.

Please check back.

The information will be available soon.

Please check back.

Course Materials

Blomquist
Fundamentals of Plant Systems.pdf
Braun
Discovery of Fission and CP-1.pdf
Safety, Licensing, Regulation.pdf
Safety Culture in an Operating Organization.pdf
INPO report on lessons learned from Fukshima.pdf
Fukuchima.pdf
Cavlina
Computer Models for Safety Analyses.pdf
DSA Events Analysis.pdf
Plant modification.pdf
User Effects.pdf
Cunningham
Regulatory experiences internal and external hazards.pdf
Use of PSA.pdf
D'Auria
safety-assessment.pdf
areas-for-safety-assessment.pdf
BEPU.pdf
bases-of-unc-approaches.pdf
SF-IC-modeling.pdf
unc-methods-results.pdf
Brunett
L.3.3.A Relationship Between Level 1 Level 2 PSA.pdf
L.3.3.B LEVEL 2 PSA.pdf
L.3.3.C Overview of Severe Accident Codes in US.pdf
L.3.4 Level 3 PSA.pdf
Bucknor
L.3.2.7-8 Fire and Flood Risk Assessments.pdf
L.3.2.9 External Events Risk Analyses.pdf
Dusic
DSA in SS.pdf
Extended BEPU.pdf
Precursors.pdf
SAMGs.pdf
Falvo
PSA at Exelon.pdf
Grabaskas
Lecture 1.pdf
Lecture 2.pdf
Lecture 3.pdf
Lecture 4.pdf
Lecture 5.pdf
FT_Example.pdf
Kling
DSA and PSA in Decision-Making Process.pdf
Event Classification.pdf
Overview of DSA in New US Plants.pdf
Overview of SMRs.pdf
Shutdown Risk Issues.pdf
Kovacs
Analysis of L1 PSA results.pdf
HRA.pdf
Introduction to PSA.pdf
System analysis.pdf
Lyubarskiy
L 3.2.12 PSA Software Overview.pdf
L 3.7 PSA in the IAEA Safety Publications.pdf
Moiseytseva
RIDM in Nuclear Industry.pdf
Preston
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 2.pdf
L3.5 IRiDM.pdf

Course Photo

The information will be available after the course end.

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