Design basis accidents for light water reactors and numerical simulation tools

Course	009
Title	Design Basis Accidents for Light Water Reactors and Numerical Simulation Tools
Prerequisites	Thermal hydraulic of nuclear reactors, nuclear power plants
Goal of the course	Familiarization with the theoretical basis and practical use of thermal hydraulic system codes such as RELAP5, TRACE for the analysis of design basis accidents of nuclear power plants
Content	Reactor safety fundamentals Safety analysis and deterministic analysis methodologies Design basis accidents and their classification Numerical simulation tools for the analysis of design basis accidents Physical and mathematical models of thermal hydraulic system codes Validation and uncertainty quantification of system codes Stepwise approach for the development of integral LWR plant models Hands-on training developing and running plant models for BWR and PWR Code systems to be used: e.g. RELAP5, TRACE, SNAP (GUI Pre- and Postprocessor)
Lecturers:	Dr. Victor Hugo Sanchez Espinoza (Head of Group Reactor Physics and Dynamics of INR, Lectureship at KIT Mechanical Engineering Faculty on Reactor Safety) Areas of Expertise: Modelling and Simulation of Research Reactors, LWR and innovative reactors e.g. SMR Accident analysis of LWR-transient and severe accidents Multi-physical and multi-scale methods for reactor safety Validation, qualification and uncertainty quantification of numerical codes
Kontact: Email: Homepage:	Dr. V. Sánchez Espinoza victor sanchez∂kit edu www.inr.kit.edu
Schedule	May, 20^th to 22^th, 2019; 9 am to 5 pm daily
Location	KIT Campus North, IKET, Building 419, Room 103

Dead line for application: May, 6^th, 2019

Application form download

Examples of TRACE Applications for PWR including Uncertianty Quantification with SUSA

plant model

TRACE/SUSA: Uncertainty Quantification of best-estimate codes: Cladding temperature for LOCA

SNAP: Animation of PWR-Integral plant model

SNAP: 3D Coolant Temperature in the Core