Travis Greene is a Research and Development Associate in the Criticality Safety Analysis and Research Group at Oak Ridge National Laboratory (ORNL). His work focuses on critical benchmark experiments, sensitivity and uncertainty (S/U) analysis, and validation and testing of nuclear data and neutron transport codes.
Travis supports the SCALE code system through testing and development of CSAS, TSUNAMI, and Sampler modules. He also contributes to the maintenance of the VALID database, provides training instruction, and prepares nuclear criticality safety validation reports.
His areas of expertise include modeling and simulation for criticality safety validation, S/U analysis, and nuclear data testing.
Links
Publications
Sep, 2026
Conference Paper
Hybrid Method for Eigenvalue Sensitivity Coefficient Calculations: Part II
Sep, 2026
Conference Paper
Updated Guidance on Sensitivity/Uncertainty Methods Use for Nuclear Criticality Safety Validation