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
Operator competitiveness
Safety excellence
Efficiency of operation
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
Related solutions
Fuel and core analyses, calculations, codes
Benefit from our advanced nuclear methods for fuel assembly design, core design, safety analysis and core monitoring
View 26 Products.Nuclear core, fuel and fuel services: trainings
With Framatome's certified training courses, train your staff with the most advanced simulation tools providing a virtual view of complex nuclear systems.
Click here for our fuel academy catalog
Training comprehensive offer
With Framatome's certified training courses, train your staff with the most advanced simulation tools providing a virtual view of complex nuclear systems.
See our global training offer