Design basis accidents for light water reactors and numerical simulation tools
Dr. V. Sanchez-Espinoza, INR, KIT |
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 |
|
Lecturer |
Dr. V. Sanchez-Espinoza, INR, KIT |
Schedule |
(23.01. - 27.01.2017); 9 am to 5 pm daily |
Location |
KIT Campus North, FTU, Building 101, Room 155 |
Dead line for application: 09.01.2017
Application form download
Examples of TRACE Applications for PWR including Uncertianty Quantification with SUSA
TRACE PWR Integral Plant Model for Safety Evaluations | TRACE/SUSA: Uncertainty Quantification of best-estimate codes: Cladding temperature for LOCA |
Lecturer: |
Dr. Victor Hugo Sanchez Espinoza |
Areas of Expertise | - Modeling of LWR in-vessel severe accident phenomena - Improvement of thermal hydraulic system codes - Transient analysis for PWR and BWR with system and coupled codes - Transient analysis of Gen-4 reactors with thermal hydraulic system codes - Development of multi-physical and multi-scale coupling for local prediction of pin power - Validation, qualification and uncertainty quantification of thermal hydraulic and neutron kinetics coupled codes |
Lectureship | KIT Mechanical Engineering Faculty since 2008: Nuclear Safety Assessment of Nuclear Power Plants |
Kontact: Email: Homepage: |
Dr. V. Sánchez Espinoza victor sanchez∂kit edu www.inr.kit.edu |