Reference No: A3141

Training: fuel and core thermal - hydraulics

Main description

Framatome is now offering a curriculum of engineering training courses covering all disciplines relevant to fuel design and operation. The courses are tailored to the major plant designs Framatome supports with fuel.

A variety of focused courses on various aspects of thermal-hydraulics aspects in the core are now available.

Click here for Advanced BWR Fuel Thermal-Hydraulic Design Training
Click here for Advanced PWR Fuel Thermal-Hydraulic Design Training
Click here for COBRA-FLX™ Thermal Hydraullic Subchannel Code Overview Training
Click here for Critical Heat Flux (CHF) Training
Click here for Cycle-Specific Steam-Line-Break Analysis Training
Click here for Departure from Nucleate Boiling and Fuel Centerline Melt Analysis Training
Click here for Form Loss Coeffcients (FLC) Training
Click here for Fuel Centerline Melt Limit and Limiting Axial Analysis Training
Click here for Mixed Core Analysis with COBRA-FLX™ Training
Click here for New TH Reload Process Overview for CE and Westinghouse Plants Training
Click here for Rod Ejection Methodology (REA) Training
Click here for Statistical Setpoint Verification for CE Plants Training
Click here for Statistical Setpoint Verification for Westinghouse Plants Training
Click here for Technical Safety Boundary Conditions for the Design and the Operation of Siemens/KWU PWR Reactors Training
Click here for XCOBRA-IIIC Model Development Training

Catalog Segmentation

CUSTOMER BENEFITS

  • Challenge solving Challenge solving
  • Operator competitiveness Operator competitiveness
  • Safety excellence Safety excellence
  • Efficiency of operation Efficiency of operation
  • Expertise Expertise
  • Challenge solving
  • Expertise

Sub-Products

Advanced Fuel Thermal-Hydraulic Design

COBRA-FLX™ Thermal Hydraullic Subchannel Code Overview

Critical Heat Flux (CHF)

Cycle-Specific Steam-Line-Break Analysis

Departure from Nucleate Boiling and Fuel Centerline Melt Analysis

Form Loss Coeffcients (FLC)

Fuel Centerline Melt Limit and Limiting Axial Analysis

Mixed Core Analysis with COBRA-FLX™

New TH Reload Process Overview for CE and Westinghouse Plants

Rod Ejection Methodology (REA)

Statistical Setpoint Verification

Technical Safety Boundary Conditions for the Design and the Operation of Siemens/KWU PWR Reactors

XCOBRA-IIIC Model Development