Tailored Course on Numerical Tools for Design Basis Accidents: Migration from RELAP5 to TRACE

RELAP5

  

Dr. Sanchez-Espinoza

Dr. V. Sanchez-Espinoza, INR, KIT

 

Course

009

Title

Tailored Course on Numerical Tools for Design Basis Accidents: Migration from RELAP5 to TRACE

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 pressurized light water reactors

Content
  • Safety Assessment of NPPs
  • TH-KN Coupled Codes for safety demonstration
  • TRACE Models and Components
  • Main differences between RELAP5 and TRACE
  • SNAP Pre- and Postprocessor

Modelling a NPP with RELAP5 and TRACE

  • Pin and FA model (R5 vs. TRACE)
  • Core model (R5 vs. TRACE)
  • RPV model (R5: 1D vs. TRACE: 3D)
  • Point Kinetics (R5 vs. TRACE)
  • Primary circuit (R5 vs. TRACE)
  • Secondary model (R5 vs. TRACE)
  • SDV/SRV model (R5 vs. TRACE)
  • PZR model (R5 vs. TRACE)
  • Signal, Trips and controllers (R5 vs. TRACE)

How to reach steady state and animation of results using SNAP

LOCA modelling

  • Break modelling (R5 vs. TRACE)
  • ECCS modelling (R5 vs. TRACE)
  • Evaluation of main results (Animation with SNAP)

    TRACE Numerics Option for parametric studies (using SNAP)

TRACE Documentation of model using SNAP

Evaluation of results using APTPLOT Scripts

Lecturer

Dr. V. Sanchez-Espinoza, INR, KIT

Schedule

19.09. - 23.09.2016; 9 am to 5 pm daily
Location

Brussels, Belgium at TRACTEBEL Site

Dead line for application:  closed

Additional information: course is already full booked.

Application form download

 

Examples of TRACE Applications for PWR including Uncertianty Quantification with SUSA

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
Head of Group “Reactor Physics and Dynamics"
Project Leader “LWR Methods and Analysis”
Dr.-Ing. in Nuclear Engineering of TU Dresden
Dipl.-Ing. Nuclear Engineering, TU Dresden
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