William BJ J Marshall

B.J. Marshall

William BJ J Marshall

Senior R&D Staff

Bio

B.J. Marshall has been at Oak Ridge National Laboratory since June, 2010.  His primary work areas include SCALE testing and training, validation of computational methods, the criticality safety of commercial spent nuclear fuel storage and transportation,  and the application of sensitivity/uncertainty methods to criticality safety.  B.J. is also involved in nuclear data testing and is also increasingly involved in support of the Department of Energy's Nuclear Criticality Safety Program (NCSP) in research, modeling and simulation, and training roles.

Prior to his time at ORNL, B.J. spent nearly 4 years at the Westinghouse Electric Company working on spent fuel pool criticality safety and PWR reload analysis.  B.J. also spent 4.5 years at Knolls Atomic Power Laboratory, primarily working on reactor physics for new reactor designs.

He holds a Doctor of Philosophy in Nuclear Engineering (December, 2017) and a Master of Science degree in Nuclear Engineering (August, 2001) from the University of Tennessee-Knoxville, and a Bachelor of Science degree in Nuclear Engineering (December, 1999) from the University of Missouri-Rolla (now the Missouri University of Science and Technology).

Projects

Criticality safety for fresh and spent light-water reactor (LWR) fuel
SCALE testing and validation, particularly criticality safety and burunp credit sequences
SCALE training
Application of sensitivity/uncertainty (S/U) tools to criticality safety, particularly criticality safety validation
Development and application of critical experiment correlations to criticality safety validation
Development and testing of covariances for nuclear data
Validation of computational methods in criticality safety

Publications

W.J. Marshall, J.B. Clarity, and S.M. Bowman, “Validation of keff Calculations for Extended BWR Burnup Credit,” NUREG/CR-7252 (ORNL/TM-2018/797), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, TN (2018).

W.J. Marshall and A.M. Holcomb, “A Testing Trifecta: Data, Codes, and Evaluations,” Trans. Am. Nucl. Soc. 119, 724-727 (2018).

W.J. Marshall, J.B. Clarity, and E.M .Saylor, “Sensitivity Calculations for Systems with Fissionable Reflector Materials Using TSUNAMI,” Trans. Am. Nucl. Soc. 119, 787-790 (2018).

E.L. Jones, J.B. Clarity, W.J. Marshall, B.T. Rearden, and G.I. Maldonado, “A Case Study in the Application of TSUNAMI-3D – Part 3, Continuous Energy – Iterated Fission Probability Method,” Trans. Am. Nucl. Soc. 119, 845-848 (2018).

E.M. Saylor, W.J. Marshall, J.B. Clarity, J.B. Clarity, Z.J. Clifton, and B.T. Rearden, “Criticality Safety Validation of SCALE 6.2.2,” ORNL/TM-2018/884, Oak Ridge, TN (2018).

W.J. Marshall, “The Case for and Against a Gadolinium Bias in SCALE: Opening Arguments,” Trans. Am. Nucl. Soc. 118, 554-557 (2018).

W.J. Marshall and E.M. Saylor, “Enhanced Engineering Analyses with Visualization of Geometry and Mesh-Based Data in Fulcrum,” Trans. Am. Nucl. Soc. 118, 987-990 (2018).

Z.J. Clifton, W.J. Marshall, and I. Hill, “Benchmark Model Temperatures Incorporated into DICE,” Trans. Am. Nucl. Soc. 118, 543-546 (2018).
E.M. Saylor, W.J. Marshall, Z.J. Clifton, J.B. Clarity, and B.T. Rearden, “Validation of KENO V.a and KENO-VI in SCALE 6.2.2 using ENDF/B-VII.0 and ENDF/B-VII.1 Libraries,” Trans. Am. Nucl. Soc. 118, 571-574 (2018).

C.M. Perfetti, B.T. Rearden, and W.J. Marshall, “Estimating Computational Biases for Criticality Safety Applications with Few Neutronically Similar Benchmarks,” Trans. Am. Nucl. Soc. 118, 561-564 (2018).

B.J. Ade, W.J. Marshall, G. Ilas, B.R. Betzler, and S.M. Bowman, “Impact of Operating Parameters on Extended BWR Burnup Credit,” NUREG/CR-7240 (ORNL/TM-2017/46), prepared for the U. S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, TN (2018).

J.B. Clarity, K. Banerjee, H.K. Liljenfeldt, and W.J. Marshall, “As-Loaded Criticality Margin Assessment of Dual-Purpose Canisters Using UNF-ST&DARDS,” Nucl. Tech., 199(3), 245 – 275 (2017).

W.J. Marshall, D.E. Mueller, J.B. Clarity, and S.M. Bowman, “Development of Criticality Safety Validation Guidance for NRC-Regulated Activities,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

W.J. Marshall, B.T. Rearden, and R.E. Pevey, “Determination of Critical Experiment Correlations for Experiments Involving Arrays of Low-Enriched Fuel Rods,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

W.J. Marshall, B.T. Rearden, and R.E. Pevey, “Determination of Critical Experiment Correlations for Experiments Involving Highly Enriched Uranium Solutions,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

B.J. Ade, W.J. Marshall, and S.M. Bowman, “The Effect of Modeling Assembly-Specific Parameters in Extended BWR Burnup Credit Analyses,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

J.B. Clarity, K. Banerjee, W.J. Marshall, and H.K. Liljenfeldt, “A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

A. Holcomb, D. Wiarda, and W.J. Marshall, “ENDF/B-VIII.0 Testing With AMPX and SCALE,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

R.A. Lefebvre and W.J. Marshall, “Template Engine Applied to Rapid Modeling,” Proceedings of NCSD 2017: Criticality Safety – pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (2017).

B.T. Rearden, B.R. Betzler, M.A. Jessee, W.J. Marshall, U. Mertyurek, and M.L. Williams, “Accuracy and Runtime Improvements with SCALE 6.2,” Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea (2017).

C.M. Perfetti, B.T. Rearden, and W.J. Marshall, “Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates,” Nucl. Sci. and Eng., 185(1) (2017).

E.L. Jones, W.J. Marshall, B.T. Rearden, M.E. Dunn, and G.I. Maldonado, “A Case Study in the Application of TSUNAMI-3D – Part 2, Continuous Energy,” Trans. Am. Nucl. Soc. 115, 677-680 (2016).

W.J. Marshall, E.L. Jones, B.T. Rearden, and M.E. Dunn, “A Case Study in the Application of TSUNAMI-3D – Part 1, Multigroup,” Trans. Am. Nucl. Soc. 115, 673-676 (2016).

J.A. Hanna, R.A.L. Rosenthal, W.J. Marshall, D.E. Mueller, E.L. Jones, S.R. Blair, and B.T. Rearden, “Validation for 233U-Fueled Systems in KENO V.a in SCALE 6.2,” Trans. Am. Nucl. Soc. 115, 665-668 (2016).

W.J. Marshall, B.J. Ade, and S.M. Bowman, “Study of Axial Burnup Profile Effects on BWR Burnup Credit,” Proceedings of the 18th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2016), Kobe, Japan, September 18 – 23, 2016.

W.J. Marshall, B.J. Ade, S.M. Bowman, and J.S. Martinez-Gonzalez, “Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit,” NUREG/CR-7224 (ORNL/TM-2015/544), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, TN, August 2016.

W.J. Marshall, B.J. Ade, and S.M. Bowman, “Apparent Monte Carlo Source Convergence Problem with BWR Fuel Depleted with Partial Control Blade Insertion,” Trans. Am. Nucl. Soc. 114, 475-478 (2016).

T.A. Eckleberry, W.J. Marshall, E.L. Jones, and G.I. Maldonado, “Validation of KENO Thermal Moderator Doppler Broadening Method in SCALE 6.2 Beta5 Using Continuous-Energy B-VII.1 Library,” Trans. Am. Nucl. Soc. 114, 484-487 (2016).

B.J. Ade, W.J. Marshall, J.S. Martinez, and S.M. Bowman, “Effects of Control Blade History, Axial Coolant Density Profiles, and Axial Burnup Profiles on BWR Burnup Credit,” Proceedings of PHYSOR 2016, Sun Valley, ID, May 1 – 5 2016.

W.J. Marshall, B.J. Ade, S.M. Bowman, I.C. Gauld, G. Ilas, U. Mertyurek, G. Radulescu, “Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

W.J. Marshall and B.T. Rearden, “Determination of Critical Experiment Correlations Using the Sampler Sequence Within SCALE 6.2,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

W.J. Marshall, B.T. Rearden, and E.L. Jones, “Validation of SCALE 6.2 Criticality Calculations Using KENO V.A and KENO-VI,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

W.J. Marshall, M.L. Williams, D. Wiarda, B.T. Rearden, M.E. Dunn, D.E. Mueller, J.B. Clarity, and E.L. Jones, “Development and Testing of Neutron Cross Section Covariance Data for SCALE 6.2,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

D.E. Mueller, D.G. Bowen, and W.J. Marshall, “Addressing Fission Product Validation in MCNP Burnup Credit Criticality Calculations,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

V. Sobes, B.T. Rearden, D.E. Mueller, W.J. Marshall, J.M. Scaglione, M.E. Dunn, “Upper Subcritical Calculations Based on Correlated Data,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

J.S. Martinez-Gonzalez, B.J. Ade, S.M. Bowman, I.C. Gauld, G. Ilas, W.J. Marshall, “Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark3 BWR Spent Fuel,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

B.J. Ade, W.J. Marshall, S.M. Bowman, I.C. Gauld, G. Ilas, and J.S. Martinez-Gonzalez, “Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

B.T. Rearden, K.B. Bekar, C. Celik, K.T. Clarno, M.E. Dunn, S.W.D. Hart, A.M. Ibrahim, S.R. Johnson, B.R. Langley, J.P. Lefebvre, R.A. Lefebvre, W.J. Marshall, U. Mertyurek, D.E. Mueller, D.E. Peplow, C.M. Perfetti, L.M. Petrie Jr., A.B. Thompson, D. Wiarda, W.A. Wieselquist, and M.L. Williams, “Criticality Safety Enhancements For Scale 6.2 And Beyond,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

E.L. Jones, G.I. Maldonado, W.J. Marshall, C.M. Perfetti, and B.T. Rearden, “Investigation of the Continuous-Energy Sensitivity Methods in SCALE 6.2 Using TSUNAMI-3D,” Proceedings of International Conference on Nuclear Criticality Safety, Charlotte, NC, September 13 – 17, 2015.

D. E. Mueller, W. J. Marshall, D. G. Bowen, and J. C. Wagner, “Bias Estimates in Lieu of Validation of Fission Products and Minor Actinides in MCNP keff Calculations for PWR Burnup Credit Casks,” NUREG/CR-7205 (ORNL/TM-2012/544), prepared for the U. S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September, 2015.

B.T. Rearden, L.M. Petrie, D.E. Peplow, K.B. Bekar, D. Wiarda, C. Celik, C.M. Perfetti, A.M. Ibrahim, S.W.D. Hart, M.E. Dunn, and W.J. Marshall, “Monte Carlo Capabilities of the SCALE Code System,” Annals of Nucl. Energy 82, 130-141 (2015).

V. Sobes, B.T. Rearden, D.E. Mueller, W.J. Marshall, J.M. Scaglione, and M.E. Dunn, “Upper Subcritical Limit Calculations with Correlated Integral Experiments,” Trans. Am. Nucl. Soc. 112, 467-470 (2015).

J. M. Scaglione, G. Radulescu, W. J. Marshall, and K. R. Robb, “A Quantitative Impact Assessment of Hypothetical Spent Fuel Reconfiguration in Spent Fuel Storage Casks and Transportation Packages,” NUREG/CR-7203 (ORNL/TM-2013/92), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2015.

W. J. Marshall, B. J. Ade, S. M. Bowman, I. C. Gauld, G. Ilas, U. Mertyurek, and G. Radulescu, “Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems,” NUREG/CR-7194 (ORNL/TM-2014/240), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2015.

M. L. Williams, D. Wiarda, G. Ilas, W. J. Marshall, B. T. Rearden, “Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization,” Nucl. Data Sheets, 123, 92 – 96, January 2015.

W. J. Marshall and B. T. Rearden, “Determination of Experimental Correlations Using the Sampler Sequence Within SCALE 6.2,” Trans. Am. Nucl. Soc. 111, 867-870 (2014).

W. J. Marshall and S. M. Bowman, “Validation of keff Calculations for Boiling-Water Reactor Fuel at Peak Reactivity in Transportation and Storage Casks,” Trans. Am. Nucl. Soc. 111, 883-886 (2014).

W. J. Marshall, B. J. Ade, and S. M. Bowman, “Evaluation of Peak Reactivity Analysis of Boiling-Water Reactor Fuel in Storage and Transportation Casks,” Trans. Am. Nucl. Soc. 111, 875-878 (2014).

E. L. Jones, G. I. Maldonado and W. J. Marshall, “Mixed Uranium-Plutonium Solution Validation of KENO V.a and KENO-VI in SCALE 6.1.2 and 6.2b3 Using Multigroup and Continuous-Energy ENDF/B-VII.0 Libraries,” Trans. Am. Nucl. Soc. 111, 857-860 (2014).

J. M. Scaglione, G. Radulescu, K. R. Robb, and W. J. Marshall, “Consequence Assessment of Fuel Reconfiguration for Dry Storage and Transportation Packages,” Trans. Am. Nucl. Soc. 111, 330-333 (2014).

W. J. Marshall, S. Croft, I. C. Gauld, J. Hu, C. E. Romano, A. Worrall, “Special Nuclear Material Inventory Processes at US Domestic Power Plants,” 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, GA, July 20 – 25, 2014.

M. L. Williams, G. Ilas, W.J. Marshall, and B. T. Rearden, “Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization,” Nucl. Data Sheets, 118, 341 – 345, April 2014.

W. J. Marshall and J. C. Wagner, “Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel,” Packaging, Transport, Storage and Security of Radioactive Materials, 25(1), 1 – 7, March 2014.

W. J. Marshall, D. Wiarda, C. Celik, B. T. Rearden and D. R. Wentz, “Validation of Criticality Safety Calculations with SCALE 6.2,” Proceedings of NCSD 2013: Criticality Safety in the Modern Era – Raising the Bar, Wilmington, NC, September 29 – October 3, 2013.

W. J. Marshall and B. T. Rearden, “The SCALE Verified Archived Library of Inputs and Data – VALID,” Proceedings of NCSD 2013: Criticality Safety in the Modern Era – Raising the Bar, Wilmington, NC, September 29 – October 3, 2013.

W. J. Marshall and J. C. Wagner, “Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel,” Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013), San Francisco California, August 18 – 23, 2013.

J. M. Scaglione, G. Radulescu, K. R. Robb, W. J. Marshall, J. C. Wagner, M. Flanagan, M. Aissa, Z. Li, “Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios,” Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013), San Francisco California, August 18 – 23, 2013.

J. M. Scaglione, K. R. Robb, R. A. Lefebvre, D. Ilas, G. Radulescu, W. J. Marshall, J. C. Wagner, H. E. Adkins, T. E. Michener, D. Vinson, “Integrated Data and Analysis System for Commercial Used Nuclear Fuel Safety Assessments,” Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013), San Francisco California, August 18 – 23, 2013.

W. J. Marshall and J. C. Wagner, “Consequences of Used Nuclear Fuel Failure on Criticality Safety,” Proceedings of International High-Level Radioactive Waste Management, Albuquerque, NM, April 28 – May 3, 2013.

M. L. Williams, G. Ilas, W. J. Marshall, and B. T. Rearden, “Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization,” Proceedings of the International Conference on Nuclear Data for Science and Technology, New York, NY, March 4 – 8, 2013.

W. J. Marshall and B. T. Rearden, Criticality Safety Validation of SCALE 6.1, ORNL/TM-2011/450 (Revised), Oak Ridge, Tenn., January 2013.

W. J. Marshall and J. C. Wagner, Consequences of Fuel Failure on Criticality Safety of Used Nuclear Fuel, ORNL/TM-2012/325, Oak Ridge, Tenn., April 2013.

D. E. Mueller, S. M. Bowman, W. J. Marshall, and J. M. Scaglione, Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel, NUREG/CR-7158 (ORNL/TM-2012/261), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

W. J. Marshall and J. C. Wagner, “Impact of Fuel Failure on Criticality Safety of Used Nuclear Fuel,” Proceedings of PSAM11, Helsinki, Finland, June 25-29, 2012.

W. J. Marshall and B. T. Rearden, “Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries,” Trans. Am. Nucl. Soc. 106, 456-460 (2012).

B. T. Rearden and W. J. Marshall, “Examination of Validation Outlier Cases Using the Sensitivity and Uncertainty Analysis Tools of SCALE 6.1,” Trans. Am. Nucl. Soc. 106, 461-464 (2012).

J. M. Scaglione, D. E. Mueller, J. C. Wagner, and W. J. Marshall, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions, NUREG/CR 7109 (ORNL/TM-2011/514), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

V. Kucukboyaci and B. J. Marshall, “Spent Fuel Pool Storage Calculations Using the ISOCRIT Burnup Credit Tool,” Annals of Nucl. Energy 39(1), 9-14, January 2012.

B. T. Rearden, D. A. Reed, R. A. Lefebvre, D. Mueller, and W. J. Marshall, “Scale/TSUNAMI Sensitivity Data for ICSBEP Evaluations,” in Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

V. N. Kucukboyaci and W. J. Marshall, “ISOCRIT: A Burnup Credit Tool for Spent Fuel Pool Storage Calculations,” Proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.

V. N. Kucukboyaci, W. J. Marshall, and M. G. Anness, “Criticality Calculations Supporting PWR Spent Fuel Pool Activities,” Trans. Am. Nucl. Soc. 97, 161-163 (2007).

R. E. Pevey, L. F. Miller, W. J. Marshall, L. W. Townsend, and B. Alvord, “Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation,” J. ASTM International 3(7), July 2006.

R. Pevey, L. F. Miller, B. J. Marshall, L. W. Townsend, and B. Alvord, “Shielding for a Cyclotron Used for Medical Isotope Production in China,” Radiat. Prot. Dosim. 115, 415-419 (2005).

R. Pevey, L. F. Miller, B. J. Marshall, L. W. Townsend, and B. Alvord, “Efficacy of Three-Dimensional Adjoint Biasing for a Cyclotron used for Medical Isotope Production in China,” in Proceedings of the 12th International Symposium on Reactor Dosimetry, Gatlinburg, TN, May 2005.

B. J. Marshall and L. F. Miller, “Power Distribution Calculations for Various Tantalum Loadings in the HFIR Control Blades,” in Transactions of the American Nuclear Society 2001 Annual Meeting, Milwaukee, Wisconsin, June 17-21, 2001.

H.T. Hunter, J. L. Parsons, W.J. Marshall, E. Sartori, and I. Kodeli, “Shielding Experimental Benchmark Storage, Retrieval, and Display System,” J. Nucl. Sci. and Tech. 37:Sup 1, 61-67 (2000).

H. T. Hunter, C. O. Slater, L. B. Holland, G. Tracz, W. J. Marshall, and J. L. Parsons, “Shielding Benchmark Computational Analysis,” Proceedings of Radiation Protection for Our National Priorities, 240-247 (2000).

H. T. Hunter, J. L. Parsons, W. J. Marshall, E. Sartori, and I. Kodeli, “Shielding Experimental Benchmark Storage, Retrieval, and Display System,” Proceedings of ICRS-9, Ibaraki, Japan, October 17 22, 1999.