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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 6.3.1, which is available from ORNL/RSICC and the RIST/NUCIS in Japan.  All attendees for the VERA training course must be licensed users of VERA. All currently scheduled training courses are described below.

Course Dates and Descriptions

The next SCALE training block will be held at Oak Ridge National Laboratory February 21-March 22, 2024. There will be no virtual or hybrid option for the courses. Registration fee information is available hereRegistration will open by the end of January.

February 26-March 1, 2024 (Mon-Thurs: 8am-5pm and Fri: 8am-12pm ET) - Polaris/PARCS for LWR Core Analysis

March 4-8, 2024 (Mon-Thurs: 8am-5pm and Fri: 8am-12pm ET) - SCALE Criticality Safety and Radiation Shielding 

March 11-15, 2024 (Mon-Thurs: 8am-5pm and Fri: 8am-12pm ET) - SCALE Sensitivity and Uncertainty Analysis for Criticality Safety Assessment and Validation

March 18-22, 2024 (Mon-Thurs: 8am-5pm and Fri: 8am-12pm ET) - SCALE/ORIGEN Standalone Fuel Depletion, Activation, and Source Term Analysis

Training Course Extended Descriptions

CTF Thermal-Hydraulics Code Course

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

Slide Rule for Nuclear Criticality Accident Response

Nuclear Data Fundamentals and AMPX Libraries Generation Course

VERA Molten Salt Reactor Training Course -- VERA-MSR

VERA Workshop and Users' Group Training

Best Practices in Modeling and Simulation of Nuclear Materials for Nuclear Safeguards Practitioners and Early Career Professionals