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Displaying 8 speakers out of 8
A. KOSILOV (IAEA, Vienna, Austria)
Methodology and Guidance on Nuclear Knowledge Management
Networking for education and training
A. PRYAKHIN, R. SOLLYCHIN, S.-G. MOON, A. KOSILOV (IAEA, Vienna, Austria)
Feedback and Closing Session
C. TUNIZ (ICTP, TRIESTE, ITALY) & A. PRYAKHIN (IAEA, VIENNA, AUSTRIA)
Welcoming and Introduction
L. PO (Micro-Simulation Technology, Montville, USA)
PCTRAN Simulator of a PWR with Active Safety Systems
PCTRAN Simulator of a PWR with Active Safety Systems
PCTRAN Simulator of a PWR with Active Safety Systems
PCTRAN Simulator of a PWR with Active Safety Systems
TRIGA Simulator
N. TIKHONOV (Moscow Engineering & Physics Institute, Moscow, Russian Federation)
Overview of the WWER Simulator Reactor System Equipment. Constructional and Physical Characteristics of the Core.
Overview of the WWER Simulator. Scope of the simulation, simulator display formats, distinctive features and capabilities. User interface.
WWER simulator exercises. Demonstration of transients. Review of reactor systems response.
WWER simulator exercises. Practice - Reactor trips and recovery
WWER simulator exercises. Stationary processes, fuel burnup, determination of the core major neutron-physics characterists.
WWER simulator exercises. Reactor startup from hot standby.
R. SOLLYCHIN (IAEA, Vienna, Austria)
CANDU-9 Systems and Overall Unit Control
CANDU-9 Systems and Overall Unit Control
CANDU-9 Systems and Overall Unit Control
CANDU-9 Systems and Overall Unit Control
CANDU-9 Reactor Systems and Regulation
CANDU-9 Reactor Systems and Regulation
CANDU-9 Heat Transport System and Control
CANDU-9 Heat Transport System and Control
CANDU-9 Balance of Plant Systems
Balance of Plant Systems
Advanced CANDU Reactor (ACR)
Advanced CANDU Reactor (ACR)
CANDU and ACR major unit events
S.-G. MOON (IAEA, Vienna, Austria)
Evolution of Full-Scope Simulators Development - Korean Experience
W.K. LAM (Cassiopeia Technologies Inc., Toronto, Canada)
Advanced Pressurized Water Reactor (APWR) NPP Description and Characterics. APWR Overview. Demonstrate Simulation Effects using APWR Simulator
Presentation of APWR Simulator Core Model and Demonstration of Reactor Controls and Passive Safety System Responses
Advanced PWR Simulator Exercises - (a) Hands-on Interaction with the simulator - freeze, run, IC, malfunctions, etc. (b) Review each major APWR subsystem (c) Practice power manoeuver
Advanced PWR Simulator Exercises - Trips and Recovery
APWR Simulator Malfunction Exercises - Study Abnormal/Emergency Event Evolutions, Safety Limits and Operational Guidelines
APWR Simulator Exercises (continued) - Malfunctions with special focus on Passive Safety System Responses
Advanced Boiling Water Reactor (ABWR) NPP Description and Characteristics; ABWR Overview and Potential Project; ESBWR. Demonstrate Simulation Effects using the ABWR Simulator
Presentation of ABWR Steady State Model and Dynamic Model as the mathematical basis for the simulator
ABWR Steady State Mass and Energy Model Exercise - to find out how the coolant quality plays an important role in reactor power control.
Review major ABWR Subsystems - Nuclear Boiler System, Safety Systems; Auxiliary Systems; BOP; Plant Operation. ABWR Simulator Exercises - Practice Power Manoeuver.
ABWR Simulator Exercises - Trips and Recovery
ABWR Simulator Malfunction Exercises with discussion on Safety Design Approach for: Operational Transients; Design Basis Events; Special Regulatory Mandated Event; Severe Accidents.

Organizers

Directors: Andrey Pryakhin (IAEA), Seong-Gyun Moon (IAEA), Claudio Tuniz (ICTP)