Reactor and Nuclear Systems Division

BJ Marshall

William Jay (B.J.) Marshall

R&D Staff
Nuclear Data and Criticality Safety
Reactor and Nuclear Systems Division
Nuclear Science and Engineering Directorate
Oak Ridge National Laboratory
P.O. Box 2008, Bldg. 5700
Oak Ridge, TN 37831-6170
Phone: 865.576.7872
Fax: 865.574.3527
marshallwj@ornl.gov

Curriculum Vitae

Research Interests

  • criticality safety of new and used fuel storage and transportation
  • burnup credit for LWR fuel
  • benchmarking and validation of criticality safety codes and methods
  • application of sensitivity/uncertainty methods to criticality safety
  • end user training in Scale codes related to criticality safety, sensitivity/uncertainty, and burnup credit

Education

  • M.S., Nuclear Engineering, University of Tennessee-Knoxville, August 2001
  • B.Sc., Nuclear Engineering, University of Missouri-Rolla, December 1999
  • Additional graduate class work, Deterministic and Monte Carlo Transport Theory

Publications

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, TN, April 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).

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, 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, TN, January 23.

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