Brian J Ade

Brian J Ade

R&D Staff

Bio

Brian Ade is a R&D staff researcher within the Reactor and Nuclear Systems Division of Oak Ridge National Laboratory specializing in reactor physics analyses. Prior to joining ORNL, he worked at Los Alamos National Laboratory as a student employee on a variety of topics including space reactor design, gas-cooled reactor research, and nuclear data. His current research interests include boiling water reactor burnup credit, lattice physics applications, nuclear nonproliferation, and a variety of nuclear security topics. He earned B.S. and M.S. degrees in 2007 and 2010 in Nuclear Engineering from Purdue University.

Publications

1. Ade, Brian J., et al. "Effects of Control Blade History, Axial Coolant Density Profiles, and Axial Burnup Profiles on BWR Burnup Credit." PHYSOR 2016, Sun Valley, Idaho, USA, May 01—05, 2016.
2. William (BJ) J. Marshall, Brian J. Ade, and Stephen M. Bowman, “Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit”, ORNL/TM-2015/544, May 2016.
3. Ade, Brian J., et al. "Analysis of Key Safety Metrics of Thorium Utilization in LWRs." Nuclear Technology, May 2016, vol. 194.
4. Martinez-Gonzalez, Jesus S., et al. "Impact of Modeling Choices on Inventory and In-Cask Criticality." In ICNC 2015 International Cooperation in Nuclear Criticality Safety, 2015.
5. Marshall, William BJ J., et al. "Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems." In ICNC 2015 International Cooperation in Nuclear Criticality Safety, 2015.
6. Ade, Brian J., et al. "Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit." In ICNC 2015 International Cooperation in Nuclear Criticality Safety, 2015.
7. Brian J. Ade and William BJ J. Marshall. Guidance for Treatment of Control Blade Usage in Extended BWR Burnup Credit. ORNL/SPR-2015/329. Oak Ridge, TN: Oak Ridge National Laboratory.2015.
8. Ade, Brian J. "Overview of Current Projects within NSED and RNSD." Invited seminar at Purdue University, 2015.
9. Marshall, William BJ J., Brian J. Ade and Jesus S. Martinez-Gonzalez. Guidance for Treatment of Axial Moderator Density Distributions in Extended BWR Burnup Credit. ORNL/TM-2015/76. Oak Ridge, TN: Oak Ridge National Laboratory.2015.
10. Ilas, Germina, et al. Modeling and Simulations for the High Flux Isotope Reactor Cycle 400. ORNL/TM-2015/36. Oak Ridge, TN: Oak Ridge National Laboratory.2015.
11. Betzler, Benjamin R., et al. "Optimization of Depletion Modeling and Simulation for the High Flux Isotope Reactor." In Joint International Conference Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, 2015.
12. Marshall, William BJ J., et al. Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems. ORNL/TM-2014/240. Oak Ridge, TN: Oak Ridge National Laboratory.2014.
13. Marshall, William BJ J., Brian J. Ade and Stephen M. Bowman. "Evaluation of Peak Reactivity Analysis of Boiling-Water Reactor Fuel in Transportation and Storage Casks." In 2014 ANS Winter Meeting and Nuclear Technology Expo, 2014.
14. Ade, Brian J., et al. "Safety Issues of Thorium Utilization in Commercial LWRs." In 2014 ANS Winter Meeting and Nuclear Technology Expo, 2014.
15. B. J. Ade, A. Worrall, J. Powers, S. Bowman, G. Flanagan, and J. Gehin, Safety and Regulatory Issues of the Thorium Fuel Cycle. NUREG/CR-7176, ORNL/TM-2013/543. Oak Ridge, TN: Oak Ridge National Laboratory.2013.
16. D. Wang, B. J. Ade and A. Ward. Cross Section Generation Guidelines for TRACE-PARCS. ORNL/TM-2012/518. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
17. B. J. Ade and I. C. Gauld. Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE. ORNL/TM-2011/290. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
18. D. Lee, et al. "Verification of New Doubly-Heterogeneous Self-shielding Method in SCALE." 2011 ANS Winter Meeting and Nuclear Technology Exposition, Washington, District of Columbia, USA, October 30 — November 03, 2011.
19. B. J. Ade, et al. SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations. ORNL/TM-2011/21. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
20. B. J. Ade, A Macro Reactivity-Equivalent Physical Transformation for Prismatic Gas-Cooled Nuclear Reactors Utilizing Uranium Oxycarbide Fuel, PHYSOR 2010.
21. B. J. Ade, “A Macro Reactivity-Equivalent Physical Transformation for Prismatic Gas-Cooled Nuclear Reactors,” Purdue University, Department of Nuclear Engineering, M.S. Thesis (C. Choi, advisor), 2010.
22. B. J. Ade, T. F. Marcille. MCNP Cross-section Validation. Space Technology and Application International Forum, 2008.
23. B. J. Ade, M. T. Hiatt, T. F. Marcille. TXSAMC and PTRACxs : New Monte Carlo Tools for Multigroup Cross Section Processing. Space Technology and Application International Forum, 2008.
24. B. J. Ade. Nuclear Data Evaluation for D-5 Reactor Design Projects. LANL D-5 End-of-year Review, 2007
25. B. J. Ade. MCNPX Coverage Analysis Using plusFORT. LANL Internal Publications, 2007.
26. D. I. Poston, B. J. Ade, P. Sadasivan, K. J. Leichliter, and D. D. Dixon. Water and regolith shielding
27. for surface reactor missions. volume 813, pages 953–966. AIP, 2006.
28. Numerous SCALE/TRITON Training Classes (teaching)
29. Numerous ORNL and LANL internal letter reports.

Internal reports
1. Ade, Brian J., et al. “Reactor Venture Framework Development: Current Progress”, ORNL/SR-2016/182, submitted to NA-22 HQ, May 2016.
2. B. J. Ade, et al. Safety and Regulatory Issues of the Thorium Fuel Cycle (Task 1: Collection of Current Information). ORNL/LTR-2013/37. Oak Ridge, TN: Oak Ridge National Laboratory.2013.
3. B. J. Ade and K. S. Kim. Assessment of the Applicability of the SCALE Computer Code System to Small Modular Reactor Design (Task 3: Demonstration of Current Capability). ORNL/LTR-2013/21. Oak Ridge, TN: Oak Ridge National Laboratory.2013.
4. W. A. Wieselquist, et al. Unified Testing for SCALE and PARCS Development Work Benchmark Package. ORNL/LTR-2013/8. Oak Ridge, TN: Oak Ridge National Laboratory.2013.
5. B. J. Ade and K. S. Kim. Assessment of the Applicability of the SCALE Computer Code System to Small Modular Reactor Design (Task 2: Evaluation of current TRITON/Polaris Cross-Section Processing Applicability and Nodal Data Generation to SMR and Identification of Gaps. ORNL/LTR-2012/596. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
6. B. J. Ade, et al. Generation of Collapsed Cross Sections for Hatch 1 Cycles 1-3. ORNL/LTR-2012/559. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
7. B. J. Ade and H. J. Smith. Generation and Testing of Lattice Parameters for SVEA-96 Optima2 Fuel - Task 1a. ORNL/LTR-2012/224. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
8. B. J. Ade, H. J. Smith and I. C. Gauld. Generation of Source Terms for High Burnup PWR and BWR Fuel in Long Term Cask Storage Part 1 - Project Description. ORNL/LTR-2012/217. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
9. B. J. Ade and H. J. Smith. Generation and Testing of Lattice Parameters for SVEA-96 Optima2 Fuel - Task 1b. ORNL/LTR-2012/172. Oak Ridge, TN: Oak Ridge National Laboratory.2012.
10. B. J. Ade, et al. Generation and Testing of Updated Lattice Parameters for an ABWR Core. ORNL/LTR-2011/529. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
11. R. T. Jubin, et al. Milestone Report - M41SW061502 - Provide input to system analysis milestones as requested . ORNL/LTR-2011/421. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
12. B. J. Ade and M. A. Jessee. Generation and Testing of Lattice Parameters for Crystal River Three Extended Power Uprate. ORNL/LTR-2011/33. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
13. B. J. Ade and M. A. Jessee. Generation and Testing of Lattice Parameters for Maximum Extended Load Line Limit Analysis Plus for a BWR. ORNL/LTR-2011/32. Oak Ridge, TN: Oak Ridge National Laboratory.2011.
14. B. J. Ade, et al. NRC Cross-Section Production Lessons Learned. ORNL/LTR-2010/263. Oak Ridge, TN: Oak Ridge National Laboratory.2010.