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 Trace 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