Coupled Neutron Kinetics /Thermal Hydraulic Codes for Safety Assessment of Nuclear Power Plants

3D Power Distribution

Dr. V. Sanchez-Espinoza, INR, KIT

Dr. Sanchez

Course	008
Title	Coupled Neutron Kinetics /Thermal Hydraulic Codes for Safety Assessment of Nuclear Power Plants
Prerequisites	Reactor Physics, Nuclear Power Plants, Thermal Hydraulics of Nuclear Reactors
Goal of the course	Analysis of LWR Transients with Coupled Neutron Kinetics / Thermal Hydraulic Codes
Content	Introduction to the role of coupled codes in safety evaluations Deterministic safety analysis methodologies Physical modes of thermal hydraulic and neutron kinetics codes Approaches for code coupling Validation of coupled codes Working with coupled codes (simple cases) Main steps for the development of integral plant models (needed data, thermal hydraulic models, neutron kinetics models) Running coupled simulations, uncertainty quantification Code systems to be used: TRACE/PARCS
Lecturer	Dr. V. Sanchez-Espinoza, KIT-Campus Nord, INR
Schedule cancelled!	cancelled; 9 am to 5 pm daily
Location	KIT Campus North; FTU, Building 101, Room 108

Dead line for application:

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 Deputy Group Leader “Reactor Physics and Dynamics RP) at the Institute for Neutron Physics and Reactor Technology (INR) Project Leader “LWR Methods and Analysis” PhD in Nuclear Engineering of TU Dresden Dipl.-Ing. Nuclear Engineering, Dresden University of Technology (TUD
Areas of Expertise	Development and Validation of Multi-physics Codes Validation and improvement of thermal hydraulic system codes Validation and improvement of subchannel codes Transient analysis for PWR and BWR with coupled codes Transient analysis of Gen-4 reactors with TH system codesModeling of LWR in-vessel severe accident phenomena
Lectureship	KIT Mechanical Engineering Faculty: • Nuclear safety I: Fundamentals • Nuclear safety II: Safety assessment of nuclear power plants
Kontakt: Email: Homepage:	Dr. V. Sánchez Espinoza victor sanchez∂kit edu www.inr.kit.edu