Reactor and Nuclear Systems Division

Mike Dunn

Mike Dunn, Ph.D.

Group Leader
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: 865.574.5260
Fax: 865.574.3527
dunnme@ornl.gov

Curriculum Vitae

Research Interests

  • Nuclear criticality safety applications analyses
  • Nuclear cross-section measurements and evaluations
  • Cross-section processing methods development and nuclear data library generation/testing
  • Monte Carlo methods and simulation

Education

  • Ph.D., Nuclear Engineering, Nuclear Criticality Safety, University of Tennessee, Knoxville, TN, 1996
  • M.S., Nuclear Engineering, Nuclear Criticality Safety, University of Tennessee, Knoxville, TN, 1994
  • B.S., Nuclear Engineering, University of Tennessee, Knoxville, TN, 1992 (top graduate in the College of Engineering)

Publications

L. C. Leal, K. H. Guber, D. Wiarda, G. Arbanas, and M. E. Dunn, "ORNL Resonance Evaluation for ENDF/B-VII.1," Trans. Am. Nucl. Soc. 106, 784-785 (2012).

G. Arbanas, M. E. Dunn, N. M. Larson, L. C. Leal, M. L. Williams, B. Becker, and R. Dagan, "Convergence of Legendre Expansion of Doppler-Broadened Double-Differential Elastic Scattering Cross Section," PHYSOR 2012 - Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012).

M. T. Pigni, M. E. Dunn, and K. H. Guber, "183W Resonance Parameter Evaluation in the Neutron Energy Range Up to 5 keV," PHYSOR 2012 - Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012).

M. B. Chadwick et al., "ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data," Nucl. Data Sheets 112(12), 2887-2996 (2011).

A. C. Kahler et al., "ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments," Nucl. Data Sheets 112(12), 2997-3036 (2011).

M. E. Dunn, L. C. Leal, K. H. Guber, G. Arbanas, D. Wiarda, R. O. Sayer, H. Derrien, and J. Harvey, "Resonance Region Cross-Section Data Advancements for Nuclear Criticality Safety Applications and ENDF/B-VII.1," Proceedings of ICNC 2011, Edinburgh, U.K., September 19-22, 2011.

T. M. Miller et al., "2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc Silene Facility," Proceedings of ICNC 2011, Edinburgh, U.K., September 19-22, 2011.

G. Arbanas, B. Becker, R. Dagan, M. E. Dunn, N. M. Larson, L. C. Leal, and M. L. Williams, "Covariance Matrix of a Double-Differential Elastic Scattering Cross Section," Proceedings of the 2nd Workshop on Neutron Cross Section Covariances, Vienna, Austria, September 14-16, 2011.

J. M. Risner, D. Wiarda, M. E. Dunn, T. M. Miller, D. E. Peplow, and B. W. Patton, Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data, NUREG/CR-7045 (ORNL/TM-2011/12), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2011.

M. E. Dunn, H. Derrien, L. C. Leal, C-S. Gil, D. Kim, "Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development," Korean Phys. Soc. 59(2), 1207-1212, August 2011.

D. Wiarda, L. C. Leal, and M. E. Dunn, "Cross-Section Covariance Data Processing with the AMPX Module PUFF-IV," Trans. Am. Nucl. Soc. 104, 772-773 (2011).

S. Goluoglu, L. M. Petrie, Jr., M. E. Dunn, D. F. Hollenbach, and B. T. Rearden, "Monte Carlo Criticality Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174, 214-235, May 2011.

J. M. Risner, D. Wiarda, T. M. Miller, D. E. Peplow, B. W. Patton, M. E. Dunn, and B. T. Parks, "Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries," Proceedings of the 14th International Symposium on Reactor Dosimetry (ISRD-14), Bretton Woods, NH, May 22-27, 2011.

G. Arbanas, M. E. Dunn, N. M. Larson, L. C. Leal, M. L. Williams, B. Becker, and R. Dagan, "Computation of Temperature-Dependent Legendre Moments of a Double-Differential Elastic Cross Section," Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

G. Arbanas, M. E. Dunn, and D. Wiarda, "Computation of Large Covariance Matrices by SAMMY on Graphical Processing Units and Multicore CPUs," Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

S. Goluoglu, J. Leppanen, L. M. Petrie, Jr., and M. E. Dunn, "SCALE Monte Carlo Eigenvalue Methods and New Advancements," Proceedings of the Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC 2010), Tokyo, Japan, October 17-21, 2010.

D. Wiarda, M. E. Dunn, D. E. Peplow, T. M. Miller, and H. Akkurt, Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6, NUREG/CR-6990 (ORNL/TM-2008/047), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2009.

D. Wiarda, G. Arbanas, L. C. Leal, and M. E. Dunn, "Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV," Nucl. Data Sheets, 109(12), 2791-2795 (2008).

M. E. Dunn, "Recent Advances in Resonance Region Nuclear Data Measurements and Analyses for Supporting Nuclear Energy Applications, Proceedings of the 2008 Annual Fall Meeting of the APS Division of Nuclear Physics, Oakland, CA, October 23-26, 2008.

M. E. Dunn and M. W. Herman, "Production and Processing of Covariance Data for Nuclear Applications by the Working Party on International Evaluation Nuclear Data Cooperation," Proceedings of PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008.

M. E. Dunn, G. Arbanas, L. C. Leal, and D. Wiarda, "Approximating Large Resonance Parameter Covariance Matrices with Group-Wise Covariance Matrices for Advanced Nuclear Fuel Cycle," Proceedings of PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008.

M. E. Dunn and M. W. Herman, "Production and Processing of Covariance Data for Nuclear Applications by the Working Party on International Evaluation Nuclear Data Cooperation," Proceedings of PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008.

R. C. Little et al., "Low-Fidelity Covariance Project," Proceedings of the Workshop on Neutron Cross Section Covariance, Port Jefferson, NY, June 24-27, 2008.

D. Wiarda, G. Arbanas, L. C. Leal, and M. E. Dunn, "Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV," Proceedings of the Workshop on Neutron Cross Section Covariance, Port Jefferson, NY, June 24-27, 2008.

L. C. Leal, H. Derrien, M. E. Dunn, and D. Mueller, Assessment of Fission Product Cross-Section Data for Burnup Credit Applications, ORNL/TM-2005/065, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

M. E. Dunn, L. C. Leal, D. Wiarda, and G. Arbanas, "Approximating Large Resonance Parameter Covariance Matrices with Group-wise Covariance Matrices for Advanced Nuclear Fuel Cycle Applications, Proceedings of the 4th Workshop on Neutron Measurements, Evaluations and Applications - Nuclear Data needs for Generation IV and Accelerator Driven Systems, NEMEA-4, Prague, Czech Republic, October 16-18, 2007.

M. E. Dunn and K. H. Guber, "Nuclear Data Measurements with the Oak Ridge Electron Linear Accelerator (ORELA) for Supporting Nuclear Fuel Cycle Applications," Proceedings of the Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators, Pocatello, ID, July 30-August 2, 2007.

D. Wiarda and M. E. Dunn, "Updated Covariance Processing Capabilities in the AMPX Code System," Proceedings of the Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators, Pocatello, ID, July 30-August 2, 2007.

M. L. Williams, B. L. Broadhead, M. E. Dunn, and B. T. Rearden "Approximate Techniques for Representing Nuclear Data Uncertainties," Proceedings of the Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators, Pocatello, ID, July 30-August 2, 2007.

S. Goluoglu, S. M. Bowman, and M. E. Dunn, "KENO Monte Carlo Code Capabilities," Trans. Am. Nucl. Soc. 97, 592-594 (2007).

S. Goluoglu, M. E. Dunn, N. M. Greene, L. M. Petrie, Jr., and D. F. Hollenbach, "Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO," Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), pp. 364-366, St. Petersburg, Russia, May 28-June 1, 2007.

S. M. Bowman, M. D. DeHart, M. E. Dunn, S. Goluoglu, J. E. Horwedel, L. M. Petrie, Jr., B. T. Rearden, and M. L. Williams, "New Criticality Safety Analysis Capabilities in SCALE 5.1," Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), pp. 403-407, St. Petersburg, Russia, May 28-June 1, 2007.

M. E. Dunn, N. M. Larson, H. Derrien, and L. C. Leal, "Perspective on Advances in Resonance-Region Nuclear Modeling and Opportunities for Future Research," Proceedings of the International Conference on Nuclear Data for Science and Technology, Nice, France, April 22-27, 2007.

M. E. Dunn, N. M. Greene, and L. M. Petrie, "Continuous-energy Version of KENO V.a for Criticality Safety Applications," Proceedings of the 7th International Conference on Nuclear Criticality Safety (ICNC 2003), Tokai-mura, Japan, October 20-24, 2003.

M. E. Dunn, PUFF-III: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices, NUREG/CR-6650 (ORNL/TM-1999/235), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2003.

L. C. Leal and M. E. Dunn, "A New Approach for Calculating Average Cross Sections in the Unresolved Energy Region," 109.pdf in Proceedings of Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Gatlinburg, Tenn., April 6-11, 2003.

M. E. Dunn and L. C. Leal, "Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods," Proceedings of the International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High Performance Computing (PHYSOR 2002), Seoul, Korea, October 7-10, 2002.

M. E. Dunn and N. M. Greene, "AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications," Trans. Am. Nucl. Soc. 86, 118-119 ( 2002).

M. E. Dunn, "Computational Experience with the Reich-Moore Resolved-Resonance Equations in the AMPX Cross-Section Processing System," Nucl. Sci. Eng. 142(1), 48-56 (September 2002).

M. E. Dunn and N. M. Greene, POLIDENT: A Module for Generating Continuous Energy Cross Sections from ENDF Resonance Data, NUREG/CR-6694 (ORNL/TM-2000/035), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2000.

M. E. Dunn, PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices, NUREG/CR-6650 (ORNL/TM-1999/235), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2000.

M. E. Dunn and B. L. Broadhead, "PUFF-III: A Multigroup Covariance Processing Code for the AMPX Cross Section Processing System," 156.pdf in Proceedings of the PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pa., May 7-12, 2000.

M. E. Dunn, N. M. Greene, and D. F. Hollenbach, "Development and Testing of a New AMPX Cross Section Processing System for Criticality Safety Applications," Trans. Am. Nucl. Soc. 81, 160-161, 1999.

M. E. Dunn and P. B. Fox, Criticality Safety Scoping Study for the Transport of Weapons-Grade Mixed-Oxide Fuel Using the MO-1 Shipping Package, ORNL/TM-13741, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1999.

M. E. Dunn, N. M. Greene, and L. C. Leal, "Energy Meshing Techniques for Processing ENDF/B-VI Cross Sections Using the AMPX Code System," Trans. Am. Nucl. Soc. 80, 140-142 (1999).

M. E. Dunn, Production of MCNP Cross Sections Using the AMPX and NJOY Processing Code Systems, ORNL/TM-6609, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 1998.

M. E. Dunn et al., "Continuous-Energy Methods Development for the Monte Carlo Code KENO V.a," Trans. Am. Nucl. Soc. 76, 234-235 (1997).