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Training
REACTOR SAFETY
SOFIA SIMULATOR TRAINING – PWR
OPERATION, PHYSICS AND SAFETY
18 – 22 May 2015 – Fontenay-aux-Roses, France
IRSN – the French Technical Safety Organization – uses a code called
CATHARE for the purpose of thermal-hydraulic analyses during a reactor
accident or safety assessments. CATHARE is a system code for PWR safety
analysis, accident management, definition of plant operating procedures and for
research and development. It is also used to quantify conservative analysis
margins and for licensing. The code is based on a 2-fluid 6-equation model
including non-condensable gas equations and additional equations for radiochemical component transport.
The IRSN engineering simulator SOFIA, designed to observe operation during
emergency situations, contains the CATHARE code to simulate the nuclear
steam supply system. It also includes hydraulic systems connected to the reactor
coolant and secondary systems, the instrumentation and control systems, the
protection and safety systems, including a part of the electric power distribution,
the containment and core neutronic behavior. This simulator benefits from toplevel multi-physics modeling, and is representative of any French-operated
nuclear power plant type, including EPR. It is a modern efficient tool for safety
assessments, training and preparation of emergency response exercises. SOFIA
is a flexible tool that can represent any other PWR types, capable of running and
studying any past accident (as Three Mile Island).
WHO SHOULD ATTEND
Head Office
12, rue de la Redoute
92260 Fontenay-aux-Roses
France
Phone: +33 (0)1 58 35 72 32
E-mail: [email protected]
Mailing Address
BP 89
92261 Fontenay-aux-Roses
Cedex
France
This training course is intended for engineers who wish to acquire general
knowledge in the operation, physics and safety of pressurized water reactors
(PWR) under normal and emergency conditions. Some basic knowledge of
PWRs would be an advantage.
The maximum number of participants for this course is eight, but two sessions
are scheduled this year.
LEARNING OUTCOMES
On completing the course, participants will:
 have a better understanding of physical phenomena occurring on PWR during
normal operation, especially during various start-up stages, and also under
emergency conditions;
 acquire an overall view of the main systems of the nuclear island used under
normal and emergency conditions, as well as their interactions;
 understand the main steps of normal operation procedures, including the
function of the main automatic controls of the plant unit, for different reactor
states (from cold shutdown for maintenance to full power operation);
 understand the main actions of operating procedures regarding safety under
emergency conditions (LOCA, SGTR);
 know and be able to assess situations that can lead to severe accidents such
as loss of cooling water, loss of steam generator feedwater, or loss of power, and
simulate the Three Mile Island and Fukushima accidents for demonstration
purposes.
PROGRAM
The five-day training sessions include class courses (2 days) and practical work on the
SOFIA simulator (3 days).
EXAMINATION
Knowledge will be tested on the full course content.
TEACHING METHODS
 Lectures, tutorial and practical work on the SOFIA simulator are combined. In
this course, class courses alternate with practical work.
 For each training session, documents are provided for class courses and
practical work, as well as electronic copies of the course.
PRICE AND REGISTRATION
 The price for this course is €4,900. This covers instruction, documentation,
technical visits and lunch and coffee breaks.
 To register complete and submit the online ENSTTI form. Select: SOFIA 2015
 Registration Deadline: 20 March, 2015
Training SOFIA
May 18-22, 2015 – Fontenay-aux-Roses, France
Type
Description
Lenght
Part 1: PWR Systems and Normal Reactor Operation
Class
courses
 A01 - Introduction to PWR Operation
Practical
work on
SOFIA
 B03 - General Information and Sequence Leading to
the Hot Shutdown State
Class
courses
 A02 - Main PWR Systems
1 day
 C01 - Description of the CATHARE Thermalhydraulic Code
 C02 - Basics of Core Physics, Divergence and Core
Control
1 day
Practical
 D03 - Divergence and Power Increase, Turbine
work on
Coupling
SOFIA
Part 2: Design Basis Accidents for PWR
Class
courses
 E01 - Description of Loss of Coolant Accidents
Practical
work on
SOFIA
 F01 - Large break LOCA Transient (LB LOCA)
Class
courses
 G01 - Description of Steam Generator Tube Rupture
(LOCA)
1 day
 F02 - Small break LOCA Transient (SB LOCA)
(SGTR) accidents
Practical
 H01 - SGTR Transient
work on
SOFIA
Part 3: Other PWR Accidents
1 day
Description of two past accidents:
Practical
work on
SOFIA
Assessment
 I01 - Loss of SG Feedwater: Reproduction TMI
Accident (SOFIA 900 MWe)
 I02 - Loss of Cooling Water and Power Supply:
Reproduction of Fukushima Accident on a PWR (SOFIA
EPR)
 J01 - Test to assess the knowledge acquired during
the training course
 J02 - Debriefing
1 day