Kaushik Banerjee

Kaushik Banerjee

Senior Research and Development Staff

Bio

Dr. Banerjee is a senior staff in the Used Fuel Systems group at Oak Ridge National Laboratory (ORNL). Banerjee received a B.E. in metallurgical engineering from the Indian Institute of Engineering Science and Technology (IIEST), shibpur (formerly the Bengal Engineering College, Shibpur) in 2001, M.S. in nuclear engineering from Kansas State University in 2005, and Ph.D. in nuclear engineering and radiological sciences from University of Michigan in 2010. Banerjee started his professional nuclear engineering career at Holtec International-a spent nuclear fuel (SNF) storage and transportation system manufacturer-as a senior nuclear engineer in 2010 and soon became the subject matter expert for radiation shielding. In late 2012, Banerjee became a principal nuclear engineer at Holtec International. At Holtec International, Banerjee led the shielding design of various SNF storage and transportation systems and was also involved in the area of the burnup credit criticality safety analysis. Banerjee joined ORNL in 2013 as an R&D staff member. Banerjee’s professional experience also includes an engineering position at a ductile cast iron pipe manufacturing facility in India. Currently, Banerjee leads the development of Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data Systems (UNF-ST&DARDS), which is a collaborative effort among multiple national laboratories and several nuclear utilities. UNF-ST&DARDS provides a comprehensive SNF database and integrated analysis tools. At ORNL, Banerjee also leads the criticality aspect of the feasibility determination of the direct disposal of already loaded SNF casks. Banerjee’s research interests include issues associated with SNF storage, transportation, and disposal, nondestructive investigation of material defects including welded SNF canisters, burnup credit criticality safety, SNF casks shielding design, Monte Carlo and deterministic radiation transport methods, and application of machine learning techniques in nuclear engineering.

Publications

Refereed Journal Articles

  1. L. Jin, K. Banerjee, S. P. Hamilton, G. G. Davidson, “Improving Variance Estimation in Monte Carlo Eigenvalue Simulation,” Annals of Nuclear Energy, 110, 692-708 (2017).
  2. J. B. Clarity, K. Banerjee, H. K. Liljenfeldt, W. J. Marshall, “As-Loaded Criticality Margin Assessment of Dual-Purpose Canisters Using UNF-ST&DARDS,” Nuclear Technology, 199(3), 245-275 (2017).
  3. J. Peterson, B. van den Akker, R. Cumberland, P. Miller, K. Banerjee, “UNF-ST&DARDS’ Unified Database and the Automatic Document Generator,” Nuclear Technology, 199(3), 310-319 (2017).
  4. G. Radulescu, K. Banerjee, R. A. Lefebvre, P. Miller, and J. M. Scaglione, “Containment Analysis Capability of UNF-ST&DARDS,” Nuclear Technology, 199(3), 299-309 (2017).
  5. G. Radulescu, K. Banerjee, R. A. Lefebvre, P. Miller, and J. M. Scaglione, “Shielding Analysis Capability of UNF-ST&DARDS,” Nuclear Technology, 199(3), 276-288 (2017).
  6. R. A. Lefebvre, J. M. Scaglione, J. L. Peterson, P. Miller, G. Radulescu, K. Banerjee, K. R. Robb, A. B. Thompson, H. Liljenfeldt, and J. P. Lefebvre, “Development of Streamlined Nuclear Safety Analyses Tool for Spent Nuclear Fuel Applications,” Nuclear Technology, 199(3), 227-244 (2017).
  7. K. Banerjee, K.R. Robb, G. Radulescu, J.M. Scaglione, J.C. Wagner, J.B. Clarity, R.A. LeFebvre, and J.L. Peterson, “Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks,” Nuclear Technology, 195(2), 124-142 (2016).
  8. K. Banerjee, and W. R. Martin, “Kernel Density Estimation Method for Monte Carlo Point Detector and Surface Crossing Flux Tallies,” Nuclear Science and Engineering, 174, 30-45 (2013).
  9. K. Banerjee, and W. R. Martin, “Kernel Density Estimation Method for Monte Carlo Global Flux Tallies,” Nuclear Science and Engineering, 170, 234-250 (2012).
  10. K. Banerjee, and W. L. Dunn, “On X-ray Back-Scattering to Detect Hidden Cracks in Multi-Layer Structures,” Applied Radiation and Isotopes, 65, 176-182 (2007).
  11. W. L. Dunn, K. Banerjee, A. Allen, and J. van Meter, “Feasibility of a Method to Identify Targets That Are Likely to Contain Conventional Explosives,” Nuclear Instruments and Methods in Physics Research B, 263, 179-182 (2007).

Conference Papers

  1. R. Cumberland and K. Banerjee, “Baselining a Spent Nuclear Fuel Cask Shielding Model,” Trans. Am. Nucl. Soc. 117(1), 1203-1205, Washington, D.C. (October 2017).
  2. G. G. Davidson and K. Banerjee, “Toward On-the-Fly Dose Analysis Using the Shift Monte Carlo Code,” Trans. Am. Nucl. Soc. 117(1), 1178-1181, Washington, D.C. (October 2017).
  3. J. B. Clarity, K. Banerjee, W. J. Marshall, H. K. Liljenfeldt, “A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS,” American Nuclear Society Nuclear Criticality Safety Division Topical Meeting, September 10-15, 2017, Carlsbad, NM.
  4. K. Banerjee, and J.M. Scaglione, “Spent Nuclear Fuel Canister Capacity: Have the Limits Been Reached?” Proc. of Institute of Nuclear Materials Management (INMM) - 58th Annual meeting, July 16-20, 2017, Indian Wells, California.
  5. J. Lei, K. Banerjee, S.P. Hamilton, and G.G. Davidson, “Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method,” Trans. Am. Nucl. Soc. 116(1), 533-535, San Francisco, CA (June 2017).
  6. R.A. Joseph, A. Myers, J. Jarrell, J. Peterson, and K. Banerjee, “SNF Data Visualization on the Centralized Used Fuel Resource for Information Exchange (CURIE) Website,” Trans. Am. Nucl. Soc. 116(1), 225-228, San Francisco, CA (June 2017).
  7. K. Banerjee, H. Liljenfeldt, P.L. Miller, J.L. Peterson, R.A. Joseph III, J.B. Clarity, G. Radulescu, R.A. Lefebvre, and J.M. Scaglione, “Consolidating Data on Spent Nuclear Fuel into a Unified Database,” Trans. Am. Nucl. Soc. 115(1), 279-282, Las Vegas, IL (November 2016).
  8. K. Banerjee, K.R. Robb, G. Radulescu, P.L. Miller, J.M. Scaglione, J.M. Cuta, and H. Liljenfeldt, “UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems,” PATRAM 2016, Japan Society of Mechanical Engineers and Atomic Energy Society of Japan, Kobe, Japan (September 2016).
  9. S.P. Hamilton, G.G. Davidson, T.M. Evans, and K. Banerjee, “Accelerated Monte Carlo Fission Source Convergence with Fission Matrix and kernel Density Estimators,” Trans. Am. Nucl. Soc. 114(1), 385-387, New Orleans, LA (June 2016).
  10. K. Banerjee, J.M. Scaglione, and J.C. Wagner, “A proposed Spent Nuclear Fuel Storage and Transportation Licensing Approach Using As-loaded Analysis,” Trans. Am. Nucl. Soc. 113, 257-271, Washington, DC (November 2015).
  11. J.B. Clarity, K. Banerjee, and J.M. Scaglione, “A Methodology for Fuel Assembly Design Characterization,” Trans. Am. Nucl. Soc. 113, 294-297, Washington, DC (November 2015).
  12. G. Radulescu, R.A. Lefebvre, P.L. Miller, A.B. Thompson, K. Banerjee, and J.M. Scaglione, “Containment Analysis Capability of UNF-ST&DARDS,” Trans. Am. Nucl. Soc. 113, 269-272, Washington, DC (November 2015).
  13. G. Radulescu, R.A. Lefebvre, K. Banerjee, P.L. Miller, and J.M. Scaglione, “Shielding Analysis Capability of UNF-ST&DARDS,” Trans. Am. Nucl. Soc. 113, 262-264, Washington, DC (November 2015).
  14. K. Banerjee and J.M. Scaglione, “Criticality Safety Analysis of As-loaded Spent Nuclear Fuel Casks,” Proceedings for International Conference on Nuclear Criticality Safety, September 2015, Charlotte, NC. 
  15. J.M. Scaglione, R.A. Lefebvre, K. Banerjee, G. Radulescu, and K.R. Robb, “A Unified Spent Nuclear Fuel Database and Analysis System,” Proceedings for International Conference on Management of Spent Fuel from Nuclear Power Reactors, June 2015, Vienna, Austria.
  16. K. Banerjee, J.M. Scaglione, J.C. Wagner, and R.A. LeFebvre, “Criticality Safety Assessment for As-Loaded Spent Fuel Storage and Transportation Casks,” The Workshop on Operational and Regulatory Aspects of Criticality safety, May 19-21 2015, Albuquerque, NM.
  17. J.M. Scaglione, J.C. Wagner, and K. Banerjee, “A Potential New Approach to Demonstrating Criticality Safety of Spent Fuel Storage and Transportation Casks,” The Workshop on Operational and Regulatory Aspects of Criticality safety, May 19-21 2015, Albuquerque, NM.
  18. 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, May 19-21 2015, Albuquerque, NM.
  19. R.T. Jubin, K. Banerjee, and T. Severynse, “Evaluation of Filler Materials to Control Post-closure Criticality of Dual Purpose Canisters,” International High-Level Radioactive Waste Management Conference, April 12-16, 2015, Charleston, SC.
  20. E.L. Hardin, E. Kalinina, R. Howard, K. Banerjee, and, J.M. Scaglione, “A Case for Direct Disposal of SNF in Existing DPCs,” International High-Level Radioactive Waste Management Conference, April 12-16, 2015, Charleston, SC.
  21. K. Banerjee, J.M. Scaglione, and J.B. Clarity, “Disposability of Loaded U.S. Dual-Purpose Canisters from a Criticality Standpoint,” International High-Level Radioactive Waste Management Conference, April 12-16, 2015, Charleston, SC.
  22. E.L. Hardin, K. Banerjee, J. Carter, R. Clark, R. Howard, E. Kalinina, and J.M. Scaglione, “Investigation of Dual-Purpose Canister Direct Disposal Feasibility,” 2015 WM Symposia, Phoenix, Arizona (14th-19th March, 2015).
  23. K. Banerjee, J.M. Scaglione, R.A. LeFebvre, G. Radulescu, and K.R. Robb, “Streamlining Analysis Capabilities for Used Nuclear Fuel Management,” 2015 WM Symposia, Phoenix, Arizona (14th-19th March, 2015).
  24. K. Banerjee, J.M. Scaglione, and R.A. LeFebvre, “Integrated Data and Analysis Tool for Used Nuclear Fuel Management,” Trans. Am. Nucl. Soc. 111, 338-341, Anaheim, CA (November 2014).
  25. J.M. Scaglione, K. Banerjee, K.R. Robb, and R.A. LeFebvre, “The Used Nuclear Fuel Storage, Transportation, and Disposal Analysis Resource and Data System,” Proc. of Institute of Nuclear Materials Management (INMM) - 55th Annual meeting, July 20-24, 2014, Atlanta, Georgia.
  26. K. Banerjee, and J.M. Scaglione, “Feasibility of Direct Disposal of Dual Purpose Canisters from Criticality Perspective,” Proc. of Institute of Nuclear Materials Management (INMM) - 55th Annual meeting, July 20-24, 2014, Atlanta, Georgia.
  27. J.M. Scaglione, J.L. Peterson, K. Banerjee, K.R. Robb, and R.A. LeFebvre, “Integrated Data and Analysis System for Commercial Used Nuclear Fuel Safety Assessments,” Proc. WM2014, Phoenix, Arizona, USA (March 2014).
  28. Gokhan Yesilyurt, Kaushik Banerjee, Etienne de Villèle, John C. Lee, and W. R. Martin, “Coupled Nuclear-Thermal-Hydraulic Calculations for VHTRs,” Trans. Am. Nucl. Soc. 102, 519-521, San Diego, California (June 2010).
  29. K. Banerjee, and W. R. Martin, “Kernel Density Estimation Method for Monte Carlo Tallies with Unbounded Variance,” Trans. Am. Nucl. Soc. 101, 430-432, Washington, DC (November 2009). (Best Paper Award).
  30. K. Banerjee, and W. R. Martin, “Applying the Kernel Density Flux Estimator to Estimate Flux at a Point,” Trans. Am. Nucl. Soc. 100, 294-296, Atlanta, Georgia (June 2009).
  31. K. Banerjee, and W. R. Martin, “Kernel Density Estimated Global Flux Tallies,” Proc. M&C Topical Meeting, American Nuclear Society, Saratoga Springs, NY (May 2009).
  32. K. Banerjee, and W. R. Martin, “Monte Carlo Global Scalar Flux Estimation with Kernel Density Estimator,” Trans. Am. Nucl. Soc. 99, 346-347, Reno, NV (November 2008). (Best Paper Award).
  33. K. Banerjee, and W. R. Martin, “A Proposed Kernel Density Estimator Method for Monte Carlo Eigenvalue Calculations,” Proc. PHYSOR-08, Interlaken, Switzerland (September 2008).