Joint ICTP-IAEA Training Course on Physics and Technology of Water Cooled Reactors through the Use of PC-based Simulators | (smr 2735)
Starts 16 Feb 2015
Ends 27 Feb 2015
Central European Time
AGH (Giambiagi Lecture Hall)
Strada Costiera, 11
I - 34151 Trieste (Italy)
The Abdus Salam International Center for Theoretical Physics (ICTP), in cooperation with the International Atomic Energy Agency (IAEA), is organizing a "Training Course on Physics and Technology of Water Cooled Reactors through the Use of PC-based Simulators" to be held at ICTP,Trieste, Italy, from 16 -27 February 2015.
PURPOSE - The purpose of the course is to provide university professors, engineers and other educators involved in teaching topics in nuclear energy with advanced computer simulation tools to help demonstrate various aspects related to reactor physics as well as operational response characteristics and safety systems associated with various types of water-cooled reactors.
FOCUS - The focus will be on educating individuals primarily from nuclear newcomer nations (i.e., countries currently involved in developing new nuclear capacity for the very first time) that are in the process of developing their nuclear education and learning centres to support the needs of both the industry and the regulator. Attendees to the course will receive the collection of IAEA nuclear power plant simulators, the associated manuals, and instructional materials. The workshop covers the physics and technology of water-cooled reactors including nuclear reactivity control, thermodynamics, stability and control in steady state and in dynamic situations, technology design and safety system design. Through the use
of the IAEA collection of PC-based simulators, workshop participants will be able to apply these
concepts to the understanding of the behaviour and response to normal operation and abnormal
conditions of a number of nuclear reactor types.
TOPICS - The main topics of the Training Course are:
• Introduction and historical background of water-cooled reactors
• Reactor physics and core design
• Thermal hydraulics and plant design
• Simulator familiarization
• Plant overview and system description (PWR, BWR, WER, CANDU)
·Plant dynamics and safety
• Normal operation and transient recovery
• Operation during accidents and malfunctions.
DELIVERY METHODS - The training course will consist of a series of lectures followed by hands-on
training exercises covering both fundamental and advanced reactor system design and response