## Kaushik Banerjee

## Kaushik Banerjee

## Biography

Kaushik Banerjee is an internationally recognized leader in the areas of nuclear waste management with experience in developing and applying mathematical and computational methods for radiation shielding, criticality safety, and reactor analyses with particular expertise in Monte Carlo radiation transport and burnup credit criticality safety analyses for spent nuclear fuel storage, transportation, and disposal.

Banerjee joined Pacific Northwest National Laboratory in 2021, as an advisor in the Nuclear Sciences Division and currently leads the Nuclear Material Storage, Transportation, and Logistics team. He has more than 15 years of experience performing research and initiating, leading, and managing major research and development projects in nuclear waste and radiation transport areas. In his current role, Banerjee provides R&D, engineering, regulatory, and policy related support to the Department of Energy Office of Nuclear Energy’s spent nuclear fuel management programs, Nuclear Regulatory Commission, and the nuclear industries.

Banerjee received a BE in metallurgical engineering from the Indian Institute of Engineering Science and Technology, Shibpur (formerly the Bengal Engineering College, Shibpur), a MS in nuclear engineering from Kansas State University, and a PhD in nuclear engineering and radiological sciences from University of Michigan. Banerjee’s professional experiences include a principal engineer position at Holtec International, and senior R&D staff and a group leader positions at Oak Ridge National Laboratory.

## Research Interest

- Spent nuclear fuel storage, transportation, and disposal
- Nuclear criticality
- Radiation shielding
- Spent nuclear fuel related data management
- Monte Carlo radiation transport

## Disciplines and Skills

- Leadership and management
- Monte Carlo simulation
- Nuclear engineering
- Project management
- Spent nuclear fuel

## Education

- PhD in nuclear engineering, University of Michigan-Ann Arbor
- MS in nuclear engineering, Kansas State University
- BE in metallurgical engineering, Indian Institute of Engineering Science and Technology

## Awards and Recognitions

- Best Summary and Presentation Award, Mathematics and Computation Division, American Nuclear Society Winter Conference, 2009
- Best Summary and Presentation Award, Mathematics and Computation Division, American Nuclear Society Winter Conference, 2008

## Publications

### 2022

- Carter J.T., K. Banerjee, and S. Peters. 2022. Spent Nuclear Fuel and Reprocessing Waste Inventory, Spent Fuel and Waste Disposition. PNNL-33938. Richland, WA: Pacific Northwest National Laboratory. Spent Nuclear Fuel and Reprocessing Waste Inventory, Spent Fuel and Waste Disposition
- Clarity J.B., H. Liljenfeldt, K. Banerjee, and P. Miller. 2022. "Validation of UNF-ST&DARDS As-Loaded Safety Analysis Methods for BWR Decay Heat Calculations." Progress in Nuclear Energy 143. PNNL-SA-164959. doi:10.1016/j.pnucene.2021.104042
- Swinney M.W., S. Bhatt, G.G. Davidson, M. Nole, and K. Banerjee. 2022. "Multiphysics Modeling of a Critical Dual-Purpose Canister in a Saturated Geological Repository." Annals of Nuclear Energy 175. PNNL-SA-165122. doi:10.1016/j.anucene.2022.109204

### 2021

- Maheras S.J., G.A. Coles, J.R. Phillips, C.A. Condon, S.M. Short, H.E. Adkins, and P.P. Lowry, et al. 2021. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment. PNNL-33524. Richland, WA: Pacific Northwest National Laboratory. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment
- Radulescu G., K. Banerjee, T. M. Miller, and D. E. Peplow. 2021. “Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3,” Nuclear Technology, 207(11), 1768-1783 (2021) (Published online: 05 Feb 2021).

### 2020

- L. Jin and K. Banerjee. 2020. “Adaptive Reweighted Variance Estimation for Monte Carlo Eigenvalue Simulations.” Nuclear Science and Engineering, 194(3), 169-180 (2020, Published online: 26 Nov 2019).
- D. E. Peplow, K. Banerjee, G. G. Davidson, I. R. Stewart, M. W. Swinney, J. N. Wagner. 2020. “Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems,” Nuclear Technology, 206(1), 107-125 (2020, Published online: 01 Jul 2019).

### 2018

- L. Jin and K. Banerjee. 2018. “Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method,” Nuclear Science and Engineering, 191(3), 248-261.
- R. M. Cumberland and K. Banerjee. 2018. “Baselining a Spent Nuclear Fuel Cask Shielding Model,” Radwaste Solutions, 25(1), 34-39, Spring 2018 (Invited).

### 2017

- L. Jin, K. Banerjee, S. P. Hamilton, G. G. Davidson. 2017. “Improving Variance Estimation in Monte Carlo Eigenvalue Simulation,” Annals of Nuclear Energy, 110, 692-708.
- J. B. Clarity, K. Banerjee, H. K. Liljenfeldt, W. J. Marshall. 2017. “As-Loaded Criticality Margin Assessment of Dual-Purpose Canisters Using UNF-ST&DARDS,” Nuclear Technology, 199(3), 245-275.
- J. Peterson, B. van den Akker, R. Cumberland, P. Miller, K. Banerjee. 2017. “UNF-ST&DARDS’ Unified Database and the Automatic Document Generator,” Nuclear Technology, 199(3), 310-319.
- G. Radulescu, K. Banerjee, R. A. Lefebvre, P. Miller, and J. M. Scaglione. 2017. “Containment Analysis Capability of UNF-ST&DARDS,” Nuclear Technology, 199(3), 299-309.
- G. Radulescu, K. Banerjee, R. A. Lefebvre, P. Miller, and J. M. Scaglione. 2017. “Shielding Analysis Capability of UNF-ST&DARDS,” Nuclear Technology, 199(3), 276-288.
- 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. 2017. “Development of Streamlined Nuclear Safety Analyses Tool for Spent Nuclear Fuel Applications,” Nuclear Technology, 199(3), 227-244.

### 2016

- K. Banerjee, K.R. Robb, G. Radulescu, J.M. Scaglione, J.C. Wagner, J.B. Clarity, R.A. LeFebvre, and J.L. Peterson. 2016. “Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks,” Nuclear Technology, 195(2), 124-142.

### 2013

- K. Banerjee, and W. R. Martin. 2013. “Kernel Density Estimation Method for Monte Carlo Point Detector and Surface Crossing Flux Tallies,” Nuclear Science and Engineering, 174, 30-45.

### 2012

- K. Banerjee, and W. R. Martin. 2012. “Kernel Density Estimation Method for Monte Carlo Global Flux Tallies,” Nuclear Science and Engineering, 170, 234-250.

### 2007

- K. Banerjee, and W. L. Dunn. 2007. “On X-ray Back-Scattering to Detect Hidden Cracks in Multi-Layer Structures,” Applied Radiation and Isotopes, 65, 176-182.
- W. L. Dunn, K. Banerjee, A. Allen, and J. van Meter. 2007. “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.