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 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.

W. J. Marshall and B. T. Rearden, Criticality Safety Validation of Scale 6.1, ORNL/TM-2011/450, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2011.

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.