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SCALE Training

Upcoming Training Courses

Training is provided by developers and expert users from the ORNL team. Courses provide a review of theory, description of capabilities and limitations of the software, and hands-on experience running problems of varying levels of complexity.

All attendees for the SCALE training courses must be licensed users of SCALE 6.2 which is available from ORNL/RSICC, the OECD/NEA Data Bank in France, and the RIST/NUCIS in Japan. 

Please request the software at least two months prior to the start of the training course.

Course Dates and Descriptions

The next training block will be held in person at Oak Ridge National Laboratory, October 2022. There will be no virtual or hybrid option for the courses. Registration fee information is available here. The registration website will be available soon.

October 3 - 7, 2022 (Mon - Thurs: 8am - 5pm, Fri: 8am - Noon ET) - SCALE/ORIGEN Standalone Fuel Depletion, Activation, and Source Term Analysis

October 10 - 14, 2022 (Mon - Thurs: 8am - 5pm, Fri: 8am - Noon ET) - SCALE Modeling and Simulation for Nuclide Inventory and Decay Heat in LWR Spent Nuclear Fuel

October 17 - 21, 2022 (Mon - Thurs: 8am - 5pm, Fri: 8am - Noon ET) - Source Terms for Advanced Reactor Spent Fuel Applications 

October 24 - 28, 2022 (Mon - Thurs: 8am - 5pm, Fri: 8am - Noon ET) - SCALE Criticality Safety Calculations

 

Training Course Extended Descriptions

Nuclear Data Fundamentals and AMPX Libraries Generation

SCALE Computational Methods for Burnup Credit

SCALE Criticality Safety Calculations

SCALE Criticality Safety and Radiation Shielding

SCALE Modeling and Simulation for Nuclide Inventory and Decay Heat in LWR Spent Nuclear Fuel

SCALE/ORIGEN Standalone Fuel Depletion, Activation, and Source Term Analysis

SCALE/Polaris Lattice Physics, Depletion, and Uncertainty Analysis

SCALE/TRITON Lattice Physics and Depletion

SCALE Sensitivity and Uncertainty Analysis for Criticality Safety Assessment and Validation

Sensitivity/Uncertainty Analysis and Uncertainty Quantification in Reactor Physics Calculations

Source Terms and Radiation Shielding for Spent Fuel Transportation and Storage Applications

Source Terms for Advanced Reactor Spent Fuel Applications