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Matthew D. Bucknor

Principal Nuclear Safety/Risk Analyst

Nuclear Engineer & Risk Analyst

Biography

Education

  • Ph.D., Nuclear Engineering, The Ohio State University, 2013
  • M.S., Nuclear Engineering, The Ohio State University, 2009
  • B.S., Electrical Engineering, The Ohio State University, 2007
  • A.S., Mechanical Drafting/Design, Technology Education College, 2000

Selected Publications

M. Bucknor, A. Brunett, D. Grabaskas, Toward a Mechanistic Source Term in Advanced Reactors: A Review of Past U.S. SFR Incidents, Experiments, and Analyses,” Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016.

A. Brunett, M. Bucknor, D. Grabaskas, Toward a Mechanistic Source Term in Advanced Reactors: Characterization of Radionuclide Transport and Retention in a Sodium Cooled Fast Reactor,” Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016.

M. Bucknor, R. Hu, A. Kraus, D. Lisowski, Comparison of RELAP5-3D Analyses to Experimental Data from the Natural Convention Shutdown Heat Removal Test Facility (NSTF),” Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016.

D. Grabaskas, M. Bucknor, J. Jerden, Regulatory Technology Development Plan Sodium Fast Reactor: Mechanistic Source Term - Metal Fuel Radionuclide Release,” Argonne National Laboratory, ANL-ART-38, February, 2016.

A. Kraus, D. Lisowski, M. Bucknor, R. Hu, Thermal-Hydraulic Simulation Framework for the NSTF and Preliminary Comparisons with Experimental Data,” 2015 American Nuclear Society Winter Meeting and Nuclear Technology Expo, Washington, D.C., November 08-12, 2015.

D. Lisowski, A. Kraus, M. Bucknor, R. Hu, Separate Effects Characterization of the NSTF to Support Computational Modeling,” 2015 American Nuclear Society Winter Meeting and Nuclear Technology Expo, Washington, D.C., November 08-12, 2015.

D. Grabaskas, M. Bucknor, A. Brunett, A. Grelle, Probabilistic Analysis of Passive Safety System Reliability in Advanced Small Modular Reactors: Methodologies and Lessons Learned,” Proceedings of the ASME 2015 Power and Energy Conversion Conference (PowerEnergy2015), San Diego, CA, June 28 – July 2, 2015.

A. Brunett, M. Bucknor, D. Grabaskas, T. Sofu, A. Grelle, A Passive System Reliability Analysis for a Station Blackout,” Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, France, May 03-06, 2015.

M. Bucknor, D. Grabaskas, A. Brunett, A. Grelle, Results of a Demonstration Assessment of Passive System Reliability utilizing the Reliability Method for Passive Systems (RMPS),” Proceedings of the International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2015), Sun Valley, ID, April 26-30, 2015.

A. Brunett, D. Grabaskas, M. Bucknor, A. Grelle, A Demonstration of Dynamic Methods for Addressing Passive Safety System Reliability,” Proceedings of the International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2015), Sun Valley, ID, April 26- 30, 2015.

D. Grabaskas, M. Bucknor, A. Brunett, Quantifying Safety Margin using the Risk-Informed Safety Margin Characterization (RISMC),” Proceedings of the International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2015), Sun Valley, ID, April 26-30, 2015.

D. Grabaskas, A. Brunett, M. Bucknor, J. Sienicki, T. Sofu, Regulatory Technology Development Plan Sodium Fast Reactor: Mechanistic Source Term Development,” Argonne National Laboratory, ANL-ART-3, February 28, 2015.

M. Bucknor, D. Grabaskas, and A. Brunett, The Development of a Demonstration Passive System Reliability Assessment,” Proceedings of the 12th International Conference on Probabilistic Safety Assessment and Management (PSAM12), Honolulu, HI, June 22-27, 2014.

A. Brunett, M. Bucknor, and D. Grabaskas, Dynamic Methods for the Assessment of Passive System Reliability,” Proceedings of the 12th International Conference on Probabilistic Safety Assessment and Management (PSAM12), Honolulu, HI, June 22-27, 2014.

M. Bucknor, R. Denning, and T. Aldemir, Modeling Fire Induced Electrical Cable Failure in Cable Bundles,” Transactions of the American Nuclear Society, San Diego, CA, November 11-15, Vol. 107, pp. 714-716, 2012.

M. Bucknor, R. Denning, and T. Aldemir, Dynamic Effects in Fire Progression Analysis,” Proceedings of the Nuclear Thermal Hydraulics, Operations, and Safety Conference (NUTHOS-9), Kaohsiung, Taiwan, September 9-13, 2012.

M. Bucknor, R. Denning, and T. Aldemir, Dynamic Considerations in the Performance of Fire PRA,” Transactions of the American Nuclear Society, Chicago, IL, June 24-28, Vol. 106, pp. 540-542, 2012.

M. Bucknor, and R. Denning, Downstream Effects – In-core Flow Blockage by Insulation Debris,” Transactions of the American Nuclear Society, Atlanta, GA, June 14-18, Vol. 100, pp. 453-454, 2009.