Reactor and Nuclear Systems Division

Don Mueller

Don Mueller

Nuclear Engineer
Nuclear Data and Criticality Safety Group
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: 865.576.4121
Fax: 865.574.3527
muellerde@ornl.gov

Curriculum Vitae

Research Interests

  • Nuclear Criticality Safety; operations, analysis, training, and calculations
  • Burnup credit in spent fuel storage and transportation
  • Sensitivity and uncertainty analysis
  • Computational method validation
  • NRC licensing of fresh and spent fuel transportation and storage
  • SCALE computer code system
  • Reactor analysis

Education

  • M.S., Nuclear Engineering, University of Illinois, 1984
  • B.Sc., Nuclear Engineering, University of Illinois, 1983
  • A.S., Engineering Science, Parkland Community College, 1981

Publications

D. E. Mueller, J. M. Scaglione, J. C. Wagner, and S. M. Bowman, Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit, NUREG/CR-7157 (ORNL/TM-2012/96), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 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), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 2013.

J. C. Wagner et al. (includes D. E. Mueller), Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy, ORNL/TM-2012/308, FCRD-FCT-2012-000232, Oak Ridge National Laboratory, December 2012.

G. T. Mays et al. (includes D. E. Mueller), Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants, ORNL/TM‑2012/237, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 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.

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

J. M. Scaglione, D. Mueller, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (keff) Predictions," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

B. T. Rearden and D. Mueller, "Uncertainty Quantification Techniques of SCALE/TSUNAMI," Trans. Am. Nucl. Soc. 104, 371-373 (2011).

V. Sobes, L. C. Leal, H. Derrien, D. Wiarda, D. Mueller, and B. Forget, "Processing and Testing New 240Pu Resolved Resonance Evaluation," Trans. Am. Nucl. Soc. 104, 780-782 (2011).

C. V. Parks, J. C. Wagner, D. Mueller, and I. C. Gauld, "Development of Technical Basis for Burnup Credit Regulatory Guidance in the United States," Proceedings of PATRAM 2010, London, U.K., October 3-8, 2010.

B. T. Rearden and D. Mueller, "Bias Assessment of 233U Systems Using a GLLS Methodology with SCALE TSURFER," Trans. Am. Nucl. Soc. 102, 307-311 (2010).

A. D. Barber and D. Mueller, "Direct Perturbation Calculation for TSUNAMI Sensitivity Coefficient Validation," Trans. Am. Nucl. Soc. 102, 281-282 (2010).

D. Mueller and B. T. Rearden, "SCALE TSUNAMI Analysis of Critical Experiments for Validation of 233U Systems," Trans. Am. Nucl. Soc. 101, 455-457 (2009).

D. E. Mueller, B. T. Rearden and D. A. Reed, "Evaluation of Fission Product Critical Experiments and Associated Biases for Burnup Credit Validation," International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 2009.

J. C. Wagner, C. V. Parks, D. E. Mueller, and I. Gauld, "Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance," International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 2009.

J. A. Roberts, P. P. H. Wilson, and D. E. Mueller, "Further Interpretation of Sensitivity Data in Support of Burnup Credit," Proceedings of the 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, Richland, Washington, September 2009.

G. Radulescu, D. E. Mueller, and J. C. Wagner, "Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit," Nucl. Technol. 167(2), 268-287, August 2009.

D. E. Mueller, B. T. Rearden, and D. F. Hollenbach, Application of the SCALE TSUNAMI Tools for the Validation of Criticality Safety Calculations Involving 233U, ORNL/TM-2008/196, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2009.

B. T. Rearden, D. E. Mueller, S. M. Bowman, R. D. Busch, and S. J. Emerson, TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE, ORNL/TM-2009/027, Oak Ridge National Laboratory, January 2009.

D. E. Mueller and B. T. Rearden, "Using Cross-Section Uncertainty Data to Estimate Biases," Trans. Am. Nucl. Soc. 99, 389-390 (2008).

J. A. Roberts and D. E. Mueller, "Designing Critical Experiments in Support of Full Burnup Credit, Trans. Am. Nucl. Soc. 99, 391-393 (2008).

L. Leal, D. Mueller, G. Arbanas, D. Wiarda, and H. Derrien, "Impact of the 235U Covariance Data In Benchmark Calculations," in Proceedings of the International Conference on the Physics of Reactors (PHYSOR '08), "Nuclear Power: A Sustainable Resource," Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, 2008.

D. E. Mueller, K. R. Elam, and P. B. Fox,Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data, NUREG/CR-6979 (ORNL/TM-2007/083), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2008.

B. T. Rearden and D. E. Mueller, "Recent Use of Covariance Data for Criticality Safety Assessment," Nuclear Data Sheets 109, 2739-2744 (2008).

D. E. Mueller, "Evaluation of the HTC Critical Experiment Data," Trans. Am. Nucl. Soc. 98, 219-222 (2008).

G. Radulescu, D. E. Mueller, and J. C. Wagner, Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit, NUREG/CR-6951 (ORNL/TM-2006/87), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

L. C. Leal, H. Derrien, M. E. Dunn, and D. E. Mueller, Assessment of Fission Product Cross-Section Data for Burnup Credit Applications, ORNL/TM-2005/65, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

G. Radulescu, D. E. Mueller, and J. C. Wagner, "Evaluation of Applicability of CRC Models for Burnup Credit Validation," Trans. Am. Nucl. Soc. 97, 151-153 (2007).

E. D. Blakeman, D. E. Peplow, J. C. Wagner, B. D. Murphy, and D. E. Mueller, PWR Facility Dose Modeling using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology, ORNL/TM-2007/133, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2007.

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, "Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation," Radwaste Solutions 14(2), 32-41 (March/April 2007).

S. N. Williams and D. E. Mueller, "Survey of Operating Parameters for Use in Burnup Credit Calculations," Trans. Am. Nucl. Soc. 95, 269-273 (2006).

D. E. Mueller and G. A. Harms, "Using the SCALE 5 TSUNAMI-3D Sequence in Critical Experiment Design," Trans. Am. Nucl. Soc. 93, 263-266 (2005).

D. E. Mueller and B. T. Rearden, "Sensitivity Coefficient Generation for a Burnup Credit Cask Model using TSUNAMI-3D," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

J. C. Wagner and D. E. Mueller, "Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel to High-Capacity Cask Designs," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

D. E. Mueller and J. C. Wagner, "Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

J. C. Wagner and D. E. Mueller, "Assessment of Benefits for Extending Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

I. C. Gauld and D. E. Mueller, Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations, ORNL/TM-2005/48, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2005.

D. A. Reed, A. W. Krass, and D. E. Mueller, "Criticality Index Determination for Transport of a Non-DOT Package of U(2.75)O2," Oak Ridge National Laboratory, May 2004.

D. A. Reed, D. E. Mueller, and R. G. Taylor, "Processing of Nuclear Ship Savannah Fuel," presented at 2004 ANS Annual meeting in Pittsburgh, June 2004.

D. E. Mueller, "Nuclear Criticality Safety at Oak Ridge National Laboratory," invited paper/presentation for the Eleventh Annual Energy Facilities Contractors Group (EFCOG) Safety Analysis Working Group (SAWG) Workshop, Milwaukee, WI, June 14-21, 2001.

D. E. Mueller, C. M. Hopper, and E. C. Crume, "MSRE Remediation or A Criticality Carol," presented at DOE NCTSP Workshop at Gaithersburg, MD, May 15, 1996.

R. L. Simmons, N. D. Jones, F. D. Popa, D. E. Mueller, and J. E. Pritchett, "Integral Fuel Burnable Absorbers with ZrB2 in Pressurized Water Reactors," Nucl. Technol. 80, 343-348, March 1988.

D. E. Mueller and W. A. Boyd, "Qualification of KENO Calculations with ENDF/B-V Cross Sections," ANS Transactions 56, 321-322, 1988.

W. A. Boyd and D. E. Mueller, "Effects of Poison Panel Shrinkage and Gaps on Fuel Storage Rack Reactivity," ANS Transactions 56, 323-324, 1988.

J. E. Pritchett and D. E. Mueller, "Operational Experience with ZrB2 Integral Fuel Burnable Absorbers," ANS Transactions 55, 117-118, 1987.

R. L. Simmons, N. D. Jones, J. E. Pritchett, D. E. Mueller, and F. D. Popa, "Integral Fuel Burnable Absorbers with ZrB2 in Pressurized Water Reactors," ANS Transactions 53, 88-89, 1986.

G. Gerdin, D. E. Mueller, and B. W. Wehring, "Charge Neutralization by Foils to Study Alpha Edge Flux Produced in a Magnetic Fusion Reactor," Fusion Technol. 7, 180-196, March 1985.

G. Gerdin, B. Wehring, T. Blue, D. E. Mueller, and D. Femia, "Charge Conversion Foil Approach to Observation of Alpha Orbit Losses," presented at the Alpha Particle Workshop, Oak Ridge National Laboratory, Knoxville, TN, February 22-23, 1984.

D. E. Mueller, "Background Considerations for a Silicon Detector Operated as a Part of an Alpha Particle Diagnostic System for the Tokomak Fusion Test Reactor," M.S. Thesis, University of Illinois, Nuclear Engineering (1984).

D. E. Mueller, G. Gerdin, B. W. Wehring, T. Emoto, and T. Blue, "A Passive Approach to Measurement of Alpha Particle Energies in TFTR," Bull. Am. Phys. Soc. 28, 1071, October 1983.