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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 virtually from Oak Ridge National Laboratory, February - March 2021. Registration fee information is available here. Please register here.

February 22 - 25, 2021 (Mon - Thurs: 9am - 12pm and 1-4 pm ET)  - SCALE/Polaris Lattice Physics, Depletion, and Uncertainty Analysis 

March 1 - 4, 2021 (Mon - Thurs: 9am - 12pm and 1-4 pm ET)  - SCALE/ORIGEN Standalone Fuel Depletion, Activation, and Source Term Analysis

March 8 - 11, 2021 (Mon - Thurs: 9am - 12pm and 1-4 pm ET) - SCALE Criticality Safety and Radiation Shielding

 

SCALE training courses offered by NEA Data Bank.

The next training block to be held virtually from the NEA Data Bank include the following courses. 

April 12 - 16, 2021 (Mon - Fri) - SCALE TSUNAMI: Sensitivity and Uncertainty Analysis for Criticality Safety Assessment and Validation, register here.

April 19 - 23, 2021 (Mon - Fri)  - SCALE ORIGEN MAVRIC: Source Terms and Radiation Shielding for Spent Fuel Transportation and Storage Applications, register here.

Training Course Extended Descriptions

SCALE Criticality Safety Calculations Course

SCALE Criticality Safety and Radiation Shielding Course

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

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 Course

Sensitivity/Uncertainty Analysis and Uncertainty Quantification in Reactor Physics Calculations

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

SCALE Computational Methods for Burnup Credit

Nuclear Data Fundamentals and AMPX Libraries Generation Course