Justin B Clarity

Justin Clarity

Justin B Clarity


Justin joined ORNL in October of 2012.  While working at ORNL Justin has worked primarily in the areas of Criticality Safety, Reactor Physics, and Spent Nuclear Fuel (SNF) Characterization.  Principal areas of focus having included:

  • Criticality margin assessment of as-loaded casks
  • Applications of burnup credit for both BWR and PWR fuel
  • NRC licensing support for wet new and spent fuel storage criticality reviews
  • Self-protection dose rate method development and application for U.S. spent fuel inventory
  • SNF data mining applications used for planning
  • Modeling of critical benchmark experiments and sensitivity and uncertainty analysis

Prior to working at ORNL Justin worked at Westinghouse Electric Company almost six years.  While at Westinghouse, Justin worked in the areas of in-core and ex-core fuel management performing criticality safety and reactor physics calculations for core reloads.


K. Banerjee, K.R. Robb, G. Radulescu, J.M. Scaglione, J.B. Clarity, and R.A. LeFebvre, “Cask-Specific Nuclear Safety Analyses of Loaded Spent Nuclear Fuel Casks,” (Accepted, Nuclear Technology).


K. Banerjee, H. K. Liljenfeldt, L. P. Miller, J. L. Peterson, R. A. Joseph, J. B. Clarity, G. Radulescu, R. A. Lefebvre, and J. M. Scaglione, Consolidating Spent Nuclear Fuel Related Data into a Unified Database, 2016 American Nuclear Society Annual Meeting, Las Vegas, NV, November 2016.


J. M. Scaglione, J. L. Jarrell, R. L. Howard, and J. B. Clarity, Overview of Security Considerations for the Back-end of the United States Fuel Cycle, Institute for Nuclear Materials Management, Atlanta, GA, July 2016.


J. B. Clarity and W. A. Wieselquist, Validation and Application of the ORIGAMI Automator for Core and Spent Fuel Pool Decay Heat and Radionuclide Source Term Calculations, ORNL/SPR-2016/32, Oak Ridge National Laboratory, January 2016.


J. B. Clarity, K. Banerjee, and J. M. Scaglione, A Methodology for Fuel Assembly Design Characterization, ANS Winter Meeting and Nuclear Technology Expo, Washington, D.C., November 2015.


J. B. Clarity, H. K. Liljenfeldt, and K. Banerjee, Criticality Process, Modeling, and Status for UNF-ST&DARDS, ORNL/SPR-2015/362, Oak Ridge National Laboratory, July 2015.


K. Banerjee, J. M. Scaglione, and J. B. Clarity, "Subcriticality Demonstration Options for Direct Disposal of Dual-Purpose Canisters," The Workshop on Operational and Regulatory Aspects of Criticality Safety, Albuquerque, NM, May 2015.


J. B. Clarity, D. E. Mueller, and J. M. Scaglione, Material At Risk Activity and Self-Protection Dose Assessment for Spent Fuel Security Applications with UNF-ST&DARDS, FCRD-MPACT-2015-000431 (ORNL/TM-2015/179), Oak Ridge National Laboratory, April 2015.


J. B. Clarity, K. Banerjee, and J. M. Scaglione, Fuel Assembly Characterization for GC-859 Incorporation in the Unified Database, FCRD-NFST-2015-00065 (ORNL/SPR-2015/32), Oak Ridge National Laboratory, January 2015.


E. L. Hardin, D. J. Clayton, R. L. Howard, J. B. Clarity, J.M Scaglione, J.T. Carter, W.M. Nutt, and R.W. Clark, "Evaluation of Direct Disposal of Spent Fuel in Existing Dual-Purpose Canisters," Radwaste Solutions 21, 26-39, January 2014.


J.M. Scaglione, A.G. Caswell, J. B. Clarity, and G. Radulescu, Considerations for an Integrated Storage, Transportation, and Disposal Canister, in Proceedings of the 14th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 28-May 2, 2013.