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Design basis accidents for light water reactors and numerical simulation tools




Design Basis Accidents for Light Water Reactors and Numerical Simulation Tools


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


  • 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)


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
Dr. V. Sánchez Espinoza
victor sanchez∂kit edu


May, 20th to 22th, 2019; 9 am to 5 pm daily


KIT Campus North, IKET, Building 419, Room 103

Dead line for application:  May, 6th, 2019

Application form download


Examples of TRACE Applications for PWR including Uncertianty Quantification with SUSA

plant model Trace SUSA
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