Guide to Performing Computational Analysis of Criticality Accident Alarm Systems ORNL/TM-2013-211 Technical Report January, 2017
Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Technical Report January, 2017
Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor (ORNL/TM-2016/742) Technical Report January, 2017
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968, ORNL/TM-2008/071) Technical Report January, 2010
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-ARIANE and REBUS Programs (UO2 Fuel) (NUREG/CR-6969, ORNL/TM-2008/072) Technical Report January, 2010
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) Technical Report January, 2010
Technical Basis for a Proposed Expansion of Regulatory Guide 3.54-Decay Heat Generation in an Independent Spent Fuel Storage Installation (NUREG/CR-6999, ORNL/TM-2007/231) Technical Report January, 2010
SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions (ORNL/TM-2010/44) Technical Report January, 2010
OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN (ORNL/TM-2010/43) Technical Report January, 2010