Researcher

John Wagner

Associate Laboratory Director

Research Areas:
Nuclear Fuels; Nuclear; Modeling and Simulation

Biography:

Dr. John C. Wagner is the laboratory director for Idaho National Laboratory. His previous roles included Associate Laboratory Director of INL’s Nuclear Science & Technology (NS&T) Directorate, director of Domestic Programs in NS&T as well as director of the Technical Integration Office for the DOE-NE Light Water Reactor Sustainability Program at INL. Wagner initially joined INL as the chief scientist at the Materials and
Fuels Complex in 2016. He has more than 20 years of experience performing research, and managing and leading research and development projects, programs and organizations.
Wagner received a B.S. in nuclear engineering from the Missouri University of Science and Technology in 1992, and M.S. and Ph.D. degrees from the
Pennsylvania State University in 1994 and 1997, respectively. Following graduate school, Wagner joined Holtec International as a principal engineer, performing criticality safety analyses and licensing activities for spent fuel storage pools and storage and transportation casks. Wagner joined the Oak Ridge National
Laboratory (ORNL) as an R&D staff member in 1999, performing research in the areas of hybrid (Monte Carlo/deterministic) radiation transport methods, burnup credit criticality safety, and spent nuclear fuel characterization and safety.
While at ORNL, Wagner held various technical leadership positions, including technical lead for postclosure criticality in support of DOE OCRWM’s Lead Laboratory for Repository Systems, Radiation Transport Methods Deputy Focus Area
lead for the Consortium for Advanced Simulation of Light Water Reactors (CASL), and national technical director of the DOE Office of Nuclear Energy’s Nuclear Fuels Storage and Transportation Planning Project. Wagner also held various management positions, including group leader for the Criticality and Shielding Methods and Applications, Radiation Transport, and Used Fuel Systems groups.
In 2014, Wagner became director of the Reactor and Nuclear Systems Division (RNSD), with responsibility for management direction and leadership to focus and integrate the seven RNSD R&D groups (Advanced Reactor Systems and Safety, Nuclear Data and Criticality Safety, Nuclear Security Modeling, Radiation
Transport, Reactor Physics, Thermal Hydraulics and Irradiation Engineering, and Used Fuel Systems) and the Radiation Safety Information Computational Center.
Wagner is a Fellow of the American Nuclear Society and recipient of the 2013 E.O. Lawrence Award. He has authored or co-authored more than 170 refereed journal and conference articles, technical reports, and conference summaries. He was the original developer of the A3MCNP and ADVANTG codes and led the development of the CADIS and Forward-Weighted CADIS hybrid transport methods.

Digital Profiles:

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Education:

Ph.D., Nuclear Engineering - Pennsylvania State University
M.S., Nuclear Engineering - Pennsylvania State University
B.S., Nuclear Engineering - Missouri University of Science and Technology (formerly University of Missouri-Rolla)

Publications:

Selected Publications

J. C. WAGNER, "Spent Nuclear Fuel Disposition," McGraw-Hill Access Science, accepted for publication (2016).

J. C. WAGNER, D. E. PEPLOW, and S. W. MOSHER, "FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations," Nucl. Sci. Eng., 176 (1), 37–57 (2014).

J. C. WAGNER, J. L. PETERSON, D. E. MUELLER, J. C. GEHIN, A. WORRALL, T. TAIWO, M. NUTT, M. A. WILLIAMSON, M. TODOSOW, R. WIGELAND, W. G. HALSEY, R. P. OMBERG, P. N. SWIFT, and J. T. CARTER, 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.

J. C. WAGNER and A. HAGHIGHAT, "Automatic Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function," Nucl. Sci. Eng., 128, 186–208 (1998).

Complete List

Ph.D. Dissertation

J. C. WAGNER, "Acceleration of Monte Carlo Shielding Calculations with an Automated Variance Reduction Technique and Parallel Processing," Ph.D. Dissertation, The Pennsylvania State University, Nuclear Engineering (December 1997).

M.S. Thesis

J. C. WAGNER, "Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence," M.S. Thesis, The Pennsylvania State University, Nuclear Engineering (December 1994).

Journal Articles

J. C. WAGNER, A. HAGHIGHAT, and B. G. PETROVIC, "Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence," Nucl. Technol., 114, 373–398 (1996).

J. C. WAGNER and A. HAGHIGHAT, "Automatic Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function," Nucl. Sci. Eng., 128, 186–208 (1998).

J. C. WAGNER and C. V. PARKS, "Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage," Nucl. Technol., 136(1), 130–140, October 2001.

J. C. WAGNER and C. E. SANDERS, "Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit," Nucl. Technol., 139(2), 91–126, August 2002.

A. HAGHIGHAT and J. C. WAGNER, "Monte Carlo Variance Reduction with Deterministic Importance Functions," Progress in Nuclear Energy, 42(1), 25–53, January 2003 [invited paper, 5^th most downloaded PNE paper in 2003].

H. P. SMITH and J. C. WAGNER, "A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem," Nucl. Sci. Eng., 149, 23–37 (2005) [invited paper].

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.

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.

J. C. WAGNER, D. E. PEPLOW and T. M. EVANS, "Automated Variance Reduction Applied to Nuclear Well-Logging Problems," Nucl. Technol., 168, 799–809 (2009).

D. E. PEPLOW, T. M. EVANS and J. C. WAGNER, "Simultaneous Optimization of Tallies in Difficult Shielding Problems," Nucl. Technol., 168, 785–792 (2009).

J. C. WAGNER, "Foreword: Special Issue on the SCALE Nuclear Analysis Code System," Nucl. Technol., 174, 125, May 2011.

A. M. IBRAHIM, M. E. SAWAN, S. W. MOSHER, T. M. EVANS, D. E. PEPLOW, P. P. H. WILSON, and J. C. WAGNER, "Global Evaluation of Prompt Dose Rates in ITER Using Hybrid Monte Carlo/Deterministic Techniques," Fusion Sci. and Technol., 60, 676–680, August 2011.

D. WANG, I. C. GAULD, G. L. YODER, L. J. OTT, G. F. FLANAGAN, M. W. FRANCIS, E. L. POPOV, J. J. CARBAJO, P. K. JAIN, J. C. WAGNER, and J. C. GEHIN, "Study of Fukushima Dai-ichi Nuclear Power Station Unit 4 Spent Fuel Pool," Nucl. Technol., 180(2), 206–215 (2012).

B. T. MERVIN, S. W. MOSHER, J. C. WAGNER, and G. I. MALDONADO, "Uncertainty Underprediction in Monte Carlo Eigenvalue Calculations," Nucl. Sci. Eng., 173, 276–292 (2013).

D. E. PEPLOW, T. M. MILLER, B. W. PATTON, and J. C. WAGNER, "Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling," Nucl. Technol., 182(1), 63–74 (2013).

J. C. WAGNER, D. E. PEPLOW, and S. W. MOSHER, "FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations," Nucl. Sci. Eng., 176 (1), 37–57 (2014).

J. L. PETERSON and J. C. WAGNER, "Characteristics of Commercial Spent Nuclear Fuel: Distributed, Diverse, and Changing with Time," Radwaste Solutions, 21(1), 50–59, January/March 2014.

B. J. MARSHALL and J. C. WAGNER, "Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel," Packaging, Transport, Storage and Security of Radioactive Material, 25(1), 1–7 (2014).

G. RADULESCU, I. C. GAULD, G. ILAS, and J. C. WAGNER, "An Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses," Nucl. Technol., 188(2), 154–171 (2014).

J. M. SCAGLIONE, D. E. MUELLER, and J. C. WAGNER, "An Approach for Validating Actinide and Fission Burnup Credit Criticality Safety Analyses – Criticality (k_eff) Predictions," Nucl. Technol., 188(3), 266–279 (2014).

A. M. IBRAHIM, P. P. H. WILSON, M. E. SAWAN, S. W. MOSHER, D. E. PEPLOW, J. C. WAGNER, T. M. EVANS, and R. E. GROVE, "Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems," Nuc. Sci. Engr., 181(1), 48–49 (2015).

K. BANERJEE, K. R. ROBB, G. RADULESCU, J. M. SCAGLIONE, J. C. WAGNER, J. B. CLARITY, R. A. LEFEBVRE, J. L. PETERSON, "Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks," Nucl. Technol., 195(2), (2016).

J. C. WAGNER, "Spent Nuclear Fuel Disposition," McGraw-Hill Access Science, accepted for publication.

Technical Reports

J. C. WAGNER, J. E. SISOLAK, and G. W. MCKINNEY, MCNP: Criticality Safety Benchmark Problems, LA-12415, Los Alamos National Laboratory, 1992.

J. C. WAGNER, E. L. REDMOND II, S. P. PALMTAG, and J. S. HENDRICKS, MCNP: Multigroup/Adjoint Capabilities, LA-12704, Los Alamos National Laboratory, 1994.

C. V. PARKS, M. D. DEHART and J. C. WAGNER, Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel, NUREG/CR-6665 (ORNL/TM-1999/303), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 2000.

J. C. WAGNER and M. D. DEHART, Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations, ORNL/TM-1999/246, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 2000.

J. C. WAGNER and C. V. PARKS, Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage, NUREG/CR-6683 (ORNL/TM-1999/230), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 2000.

J. C. WAGNER, M. D. DEHART and B. L. BROADHEAD, Investigation of Burnup Credit Modeling Issues Associated with BWR Fuel, ORNL/TM-1999/193, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 2000.

S. M. BOWMAN, I. C. GAULD, and J. C. WAGNER, Recommendations on Standardized Technical Specifications for Spent Fuel Storage Casks, NUREG/CR-6716 (ORNL/TM-2000/385), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2001.

J. C. WAGNER, Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit, NUREG/CR-6747 (ORNL/TM-2000/306), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, October 2001.

C. E. SANDERS and J. C. WAGNER, Parametric Study of the Effect of Control Rods for PWR Burnup Credit, NUREG/CR‑6759 (ORNL/TM-2001/69), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 2002.

C. E. SANDERS and J. C. WAGNER, Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit, NUREG/CR-6760 (ORNL/TM-2000/321), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2002.

J. C. WAGNER and C. V. PARKS, Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit, NUREG/CR-6761 (ORNL/TM-2000/373), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2002.

J. C. WAGNER and C. V. PARKS, Recommendations on the Credit for Cooling Time in PWR Burnup Credit Analyses, NUREG/CR-6781 (ORNL/TM-2001/272), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2003.

J. C. WAGNER and C. E. SANDERS, Assessment of Reactivity Margins and Loading Curves for PWR Burnup Credit Cask Designs, NUREG/CR-6800 (ORNL/TM-2002/006), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2003.

J. C. WAGNER, M. D. DEHART, and C. V. PARKS, Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses, NUREG/CR-6801 (ORNL/TM-2001/273), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2003.

K. R. ELAM, J. C. WAGNER, and C. V. PARKS, Scoping Studies for the Effects of Fuel Failure on Criticality Safety and Radiation Dose of Spent Fuel Casks, NUREG/CR-6835 (ORNL/TM-2002/255), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 2003.

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, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2007.

J. C. WAGNER, Technical Work Plan for Development of Technical Data Needed to Justify Full Burnup Credit in Criticality Safety Licensing Analyses Involving Commercial Spent Nuclear Fuel, DOC.20070213.0002, TWP-EBS-MD-000019, Rev. 01, prepared for the U.S. Department of Energy Office of Civilian Radioactive Waste Management by Sandia National Laboratories, Las Vegas, NV, February 2007.

J. C. WAGNER, Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask, NUREG/CR-6955 (ORNL/TM-2004/52), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 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), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2008.

B. BEVARD, J. C. WAGNER, M. AISSA and C. V. PARKS, Review of Information for Spent Nuclear Fuel Burnup Confirmation, NUREG/CR-6998 (ORNL/TM-2007/229), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, December 2009.

G. RADULESCU and J. C. WAGNER, Burn-up Credit Criticality Safety Benchmark – Phase VII: UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal, A Report by the Expert Group on Burn-up Credit Criticality NEA Nuclear Science Committee, Working Party on Nuclear Criticality Safety, ISBN 978-92-64-99172-9, NEA No. 6998, Nuclear Energy Agency, Organisation for Economic Co-operation and Development, February 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 (k_eff) Predictions, NUREG/CR-7109 (ORNL/TM‑2011/514), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2012.

G. RADULESCU, I. C. GAULD, G. ILAS, and J. C. WAGNER, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Isotopic Composition Predictions, NUREG/CR-7108 (ORNL/TM‑2011/509), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2012.

J. C. WAGNER, J. L. PETERSON, D. E. MUELLER, J. C. GEHIN, A. WORRALL, T. TAIWO, M. NUTT, M. A. WILLIAMSON, M. TODOSOW, R. WIGELAND, W. G. HALSEY, R. P. OMBERG, P. N. SWIFT, and J. T. CARTER, 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.

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.

S. W. MOSHER, A. M. BEVILL, S. R. JOHNSON, A. M. IBRAHIM, C. R. DAILY, T. M. EVANS, J. C. WAGNER, J. O. JOHNSON, and R. E. GROVE, ADVANTG – An Automated Variance Reduction Parameter Generator, ORNL/TM-2013/416, UT-Battelle, LLC, Oak Ridge National Laboratory, November 2013

S. W. MOSHER, A. M. BEVILL, S. R. JOHNSON, A. M. IBRAHIM, C. R. DAILY, T. M. EVANS, J. C. WAGNER, J. O. JOHNSON, and R. E. GROVE, ADVANTG – An Automated Variance Reduction Parameter Generator, Rev. 1, ORNL/TM-2013/416, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2015.

D. E. MUELLER, W. J. MARSHALL, D. G. BOWEN, and J. C. WAGNER, Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP K_eff_, Calculations for PWR Burnup Credit Casks, NUREG/CR-7205 (ORNL/TM-2012/544), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 2015.

Full Conference Papers

G. W. MCKINNEY, J. C. WAGNER, and J. E. SISOLAK, "MCNP/KENO Criticality Comparison," Proceedings of the Topical Meeting on Physics and Methods in Criticality Safety, Nashville, TN, September 19–23, American Nuclear Society, Order 700186, p. 207, 1993.

J. C. WAGNER, A. HAGHIGHAT, and B. G. PETROVIC, "Comparison of Monte Carlo and Synthesized 3-D Deterministic Models for Reactor Cavity Dosimetry Calculations," Proceedings of the Eighth Int. Conf. on Radiation Shielding, Arlington, TX, pp. 714–720, April 1994.

J. C. WAGNER, A. HAGHIGHAT, B. G. PETROVIC, and H. L. HANSHAW, "Benchmarking of Synthesized 3-D Sn Transport Methods for Pressure Vessel Fluence Calculations with Monte Carlo," Proceedings of the Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analyses, Portland, OR, pp. 1214–1222, May 1995 [Best Benchmark Paper Award].

A. HAGHIGHAT, H. L. HANSHAW, and J. C. WAGNER, "Multigroup Cross Section Generation with Adjoint Weighting and its Application to PV Dosimetry," 1996 Radiation Protection & Shielding Topical Meeting, No. Falmouth, MA, pp. 173–180, April 1996.

J. C. WAGNER and A. HAGHIGHAT, "Application of the Discrete Ordinates Adjoint Function to Accelerating Monte Carlo Reactor Cavity Dosimetry Calculations," 1996 Radiation Protection & Shielding Topical Meeting, No. Falmouth, MA, pp. 345–352, April 1996.

J. C. WAGNER, A. J. BARATTA, and J. W. GERDES, "Characterization of the Radiation Environment at the Army Pulse Radiation Facility with Monte Carlo," Ninth Intl. Symposium on Reactor Dosimetry, Prague, Czech Republic, pp. 762–769, September 2–6, 1996.

J. C. WAGNER and A. HAGHIGHAT, "Acceleration of Monte Carlo Reactor Cavity Dosimetry Calculations with the Discrete Ordinates Adjoint Function," Ninth Intl. Symposium on Reactor Dosimetry, Prague, Czech Republic, pp. 754–761, September 2–6, 1996.

J. C. WAGNER and A. HAGHIGHAT, "Monte Carlo PWR Cavity Dosimetry Calculations using an Automatic Variance Reduction Technique," Joint Int. Conf. on Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, pp. 1031–1039, October 6–10, 1997 [invited paper].

J. C. WAGNER and A. HAGHIGHAT, "Automatic Variance Reduction for Monte Carlo Shielding Calculations with the Discrete Ordinates Adjoint Function," Joint Int. Conf. on Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, pp. 671–680, October 6–10, 1997.

B. G. PETROVIC, A. HAGHIGHAT and J. C. WAGNER, "Definition of a Calculational 3-D Benchmark Problem for PWR Pressure Vessel Neutron Transport Calculations," Joint Int. Conf. on Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, pp. 292–301, October 6–10, 1997.

B. G. PETROVIC, J. C. WAGNER and A. HAGHIGHAT, "Verification of Improved Synthesized 3-D Sn and Monte Carlo Methods for Pressure Vessel Fast Neutron Fluence Calculations," Joint Int. Conf. on Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, pp. 1586–1595, October 6–10, 1997.

J. C. WAGNER, J. W. GERDES, and A. J. BARATTA, "Comparison of Calculated and Measured Neutron and Gamma Radiation Environments at the Army Pulse Radiation Facility," 1998 ANS Radiation Protection and Shielding Division Topical Conference, Nashville, TN, April 19–23, 1998 [invited paper].

J. C. WAGNER and A. HAGHIGHAT, "Automatic Variance Reduction for Monte Carlo Shielding Calculations," 1998 ANS Radiation Protection and Shielding Division Topical Conference, Nashville, TN, April 19–23, 1998.

A. HAGHIGHAT, H. HIRUTA, B. PETROVIC and J. C. WAGNER, "Performance of the Automated Adjoint Accelerated MCNP (A³MCNP) for Simulation of a BWR Core Shroud Problem," Proceedings of the International Conference on Mathematics and Computation, Reactor Physics, and Environmental Analysis in Nuclear Applications, Madrid, Spain, September 27–30, 1999.

C. V. PARKS, I. C. GAULD, J. C. WAGNER, B. L. BROADHEAD, M. D. DEHART, and D. D. EBERT, "Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks," Proceedings of the Twenty-Eighth Water Reactor Safety Information Meeting, Bethesda, MD, October 23–25, 2000.

A. HAGHIGHAT and J. C. WAGNER, "Application of A³MCNP to Radiation Shielding Problems," Proceedings of the International Conference on Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, Lisbon, Portugal, October 23–26, 2000.

C. V. PARKS, M. D. DEHART, and J. C. WAGNER, "Phenomena and Parameters Important to Burnup Credit," Proceedings of the Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, pp. 233–247, July 10–14, 2000, Vienna, Austria, August 2001.

C. V. PARKS and J. C. WAGNER, "Issues for Effective Implementation of Burnup Credit," Proceedings of the Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, pp. 298–308, July 10–14, 2000, Vienna, Austria, August 2001.

C. E. SANDERS and J. C. WAGNER, "Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analysis," Proceedings of the 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

C. E. SANDERS and J. C. WAGNER, "Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses," Proceedings of the 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

J. C. WAGNER, "Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety," Proceedings of the 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

C. V. PARKS, J. C. WAGNER, I. C. GAULD, B. L. BROADHEAD, and C. E. SANDERS, "U.S. Regulatory Research Program for Implementation of Burnup Credit in Transport Casks," Proceedings of the 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), Chicago, IL, September 3–7, 2001.

J. C. WAGNER, "An Automated Deterministic Variance Reduction Generator for Monte Carlo Shielding Applications," Proceedings of the American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, NM, April 12–14, 2002.

H. P. SMITH and J. C. WAGNER, "A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem," Proceedings of the Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, April 6–11, 2003, LaGrange Park, IL (2003), ISBN 0-89448-674-8, American Nuclear Society Order No. 700300.

J. C. WAGNER, "Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs," Proceedings of the 7th International Conference on Nuclear Criticality Safety (ICNC2003), pp. 684–689, October 20–24, Tokai-mura, Ibaraki, Japan JAERI-Conf 2003-019, Japan Atomic Energy Research Institute (2003).

C. V. PARKS and J. C. WAGNER, "Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation," Proceedings of the 14th Pacific Basin Nuclear Conference, Honolulu, HI, March 21–25, ANS Order #: 700305, ISBN: 0-89448-679-9 (2004).

B. L. BROADHEAD and J. C. WAGNER, "Effective Biasing Schemes for Duct Streaming Problems," International Conference on Radiation Shielding (ICRS-10), May 9–14, Funchal, Portugal (2004).

C. V. PARKS and J. C. WAGNER, "Status of Burnup Credit for Transportation of SNF in the United States," International Symposium on the Packaging & Transportation of Radioactive Materials, Berlin, Germany, September 20‑24, 2004.

J. C. WAGNER and D. E. MUELLER, "Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs," Proceedings of the 2005 Nuclear Criticality Safety Division Topical Meeting, Knoxville, TN, September 19–22, 2005.

C. V. PARKS, C. J. WITHEE, and J. C. WAGNER, "U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Cases," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, United Kingdom, August 29–September 2, 2005, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.

C. V. PARKS and J. C. WAGNER, "A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, United Kingdom, August 29–September 2, 2005.

J. C. WAGNER, C.V. PARKS and D. E. MUELLER, "Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, United Kingdom, August 29–September 2, 2005.

D. E. MUELLER and J. C. WAGNER, "Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation," Proceedings of 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, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.

J. GULLIFORD and J. C. WAGNER, "Procedural Compliance with Safety Criteria," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29–September 2, 2005, London, United Kingdom, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.

D. E. PEPLOW and J. C. WAGNER, "Automated Variance Reduction for SCALE Shielding Calculations," Proceedings of the ANS 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad, NM, pp. 556–558, April 2–6, 2006.

C. V. PARKS, J. C. WAGNER, and D. E. MUELLER, "Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation," Proceedings of the ANS 2006 International High-Level Radioactive Waste Management Conference, Las Vegas, NV, pp. 1299–1308, April 30–May 4, 2006.

H. AKKURT, J. C. WAGNER, and K. ECKERMAN, "Hand-Held Instruments for Landmine Detection: View from Radiation Dosimetry," Nuclear Instruments and Methods in Physics Research A, 579, 391–394, 2007.

Y. K. M. PENG, T. W. BURGESS, A. J. CARROLL, C. L. NEUMEYER, J. M. CANIK, M. J. COLE, W. D. DORLAND, P. J. FOGARTY, L. GRISHAM, D. L. HILLIS, Y. KATOH, K. KORSAH, M. KOTSCHENREUTHER, R. LAHAYE, S. MAHANJAN, R. MAJESKI, B. E. NELSON, B. D. PATTON, D. A. RASMUSSEN, S. A. SABBAGH, A. C. SONTAG, R. E. STOLLER, C. C. TSAI, P. VALANJU, J. C. WAGNER, and G. L. YODER, "Extensive Remote Handling and Conservative Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility," 22^nd IAEA Fusion Energy Conference, "Celebrating Fifty Years of Fusion...Entering into the Burning Plasma Era," Geneva, Switzerland, October 13–18, 2008.

S. W. MOSHER, T. M. MILLER, T. M. EVANS, and J. C. WAGNER, "Automated Weight-Window Generation for Threat Detection Applications using ADVANTG," International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009), Saratoga Springs, NY, May 3–7, 2009.

J. C. WAGNER, E. D. BLAKEMAN, and D. E. PEPLOW, "Forward-Weighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities," International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009), Saratoga Springs, NY, May 3–7, 2009.

J. M. SCAGLIONE and J. C. WAGNER, "Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain," Proceedings of the IAEA/CSN International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 27–30, 2009.

J. C. WAGNER, C. V. PARKS, I. GAULD, and D. E. MUELLER, "Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance," Proceedings of the IAEA/CSN International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 27–30, 2009.

A. M. IBRAHIM, S. W. MOSHER, T. M. EVANS, D. E. PEPLOW, M. E. SAWAN, P. P. H. WILSON, and J. C. WAGNER, "ITER Neutronics Modeling Using Hybrid Monte Carlo/SN and CAD-based Monte Carlo Methods," Proceedings of the American Nuclear Society Radiation Protection and Shielding Division 2010 Topical Meeting, Las Vegas, NV, pp. 29–32, April 18–23, 2010.

K. B. BEKAR, J. C. WAGNER, and T. M. EVANS, "Testing MCNP-BRL for Nuclear Vulnerability Assessment with the M60A1 Tank," Proceedings of the American Nuclear Society Radiation Protection and Shielding Division 2010 Topical Meeting, Las Vegas, NV, pp. 66–68, April 18–23, 2010.

A. M. IBRAHIM, D. E. PEPLOW, T. M. EVANS, P. P. H. WILSON, and J. C. WAGNER, "Improving the SN Adjoint Source and Geometry Representation Capabilities in the SCALE Hybrid Shielding Analysis Sequence," Proceedings of the American Nuclear Society Radiation Protection and Shielding Division 2010 Topical Meeting, Las Vegas, NV, pp. 88–89, April 18–23, 2010.

J. CHEATHAM and J. C. WAGNER, "Review and Ranking of NDA Techniques to Determine Plutonium Content in Spent Fuel," Proceedings of the INMM 51st Annual Meeting, Baltimore, MD, July 11–15, 2010.

C. V. PARKS, J. C. WAGNER, D. E. MUELLER, and I. C. GAULD, "Development of Technical Basis for Burnup Credit Regulatory Guidance in the United States," Proceedings of PATRAM 2010, London, United Kingdom October 3‑8, 2010.

J. C. WAGNER, S. W. MOSHER, T. M. EVANS, D. E. PEPLOW, and J. A. TURNER, "Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses," Proceedings of the Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA+MC2010), Tokyo, Japan, October 17–21, 2010.

J. C. WAGNER, D. E. PEPLOW, S. W. MOSHER, and T. M. EVANS, "Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Laboratory," Proceedings of the Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA+MC2010), Tokyo, Japan, October 17–21, 2010.

Y. K. M. PENG et al., "Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)," Proceedings of IAEA FEC-2010, Daejon, S. Korea, October 9–16, 2010.

G. RADULESCU and J. C. WAGNER, "Review of Results for the OECD/NEA Phase VII Benchmark: Study of Spent Fuel Compositions for Long-Term Disposal," Proceedings of the International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 10–14, 2011.

J. M. SCAGLIONE and J. C. WAGNER, "Review of Yucca Mountain Disposal Criticality Studies," Proceedings of the International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 10–14, 2011.

B. T. MERVIN, G. I. MALDONADO, S. W. MOSHER, and J. C. WAGNER, "Uncertainty Analyses for Localized Tallies in Monte Carlo Eigenvalue Calculations," 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.

Y. K. M. PENG, J. M. PARK, J. M. CANIK, S. J. DIEM, A. C. SONTAG, A. LUMSDAINE, Y. L. KATOH, R. W. BURGESS, K. KORSAH, B. D. PATTON, J. C. WAGNER, P. J. FOGARTY, and M. SAWAN, "Fusion Nuclear Science Facility (FNSF), Motivation and Required Capabilities," Proceedings of 2011 IEEE/NPSS 24th Symposium on Fusion Engineering (SOFE), Chicago, IL, June 26–30, 2011.

G. RADULESCU, I. C. GAULD, G. ILAS, and J. C. WAGNER, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19–23, 2011.

J. M. SCAGLIONE, D. E. MUELLER, and J. C. WAGNER, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (k_eff) Predictions," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19–23, 2011.

T. M. MILLER et al., "2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc Silene Facility," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19–23, 2011.

A. M. IBRAHIM, D. E. PEPLOW, J. C. WAGNER, S. W. MOSHER, and T. M. EVANS, "Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources," Proceedings of PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, April 15–20, 2012.

B. T. MERVIN, S. W. MOSHER, T. M. EVANS, J. C. WAGNER, and G. I. MALDONADO, "Variance Estimation in Domain Decomposed Monte Carlo Eigenvalue Calculations," Proceedings of PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, April 15–20, 2012.

N. C. SLY, B. T. MERVIN, S. W. MOSHER, T. M. EVANS, J. C. WAGNER, and G. I. MALDONADO, "Verification of the SHIFT Monte Carlo Code with the C5G7 Reactor Benchmark," Proceedings of PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, April 15–20, 2012.

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.

A. M. IBRAHIM, P. P. H. WILSON, M. E. SAWAN, S. W. MOSHER, T. M. EVANS, D. E. PEPLOW, and J. C. WAGNER, "Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Fusion Energy Systems," Proceedings of 12th International Conference on Radiation Shielding (ICRS-12), 17th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society (RPSD-2012), Nara, Japan, September 2–7, 2012.

J. C. WAGNER J. L. PETERSON, D. E. MUELLER, J. C. GEHIN, A. WORRALL, T. TAIWO, M. NUTT, M A. WILLIAMSON, M. TODOSOW, R. WIGELAND, W. G. HALSEY, R. P. OMBERG, P. N. SWIFT, and J. T. CARTER, "Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy," Proceedings of WM 2013, Phoenix, AZ, February 24–28, 2013.

M. RAHIMI, Z. LI, D. TANG, M. AISSA, M. FLANAGAN, and J. WAGNER, "Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation," Proceedings of WM2013, Phoenix, AZ, February 24–28, 2013.

J. C. WAGNER, J. L. PETERSON, D. MUELLER, J. C. GEHIN, A. WORRALL, T. TAIWO, M. NUTT, M. WILLIAMSON, M. TODOSOW, R. WIGELAND, W. HALSEY, R. OMBERG, P. SWIFT, and J. CARTER, "Assessment of Used Nuclear Fuel Inventory Relative to Disposition Options," Proceedings of the 14th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 28–May 2, 2013.

W. J. MARSHALL and J. C. WAGNER, "Consequences of Used Nuclear Fuel Failure on Criticality Safety," Proceedings of the 14th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 28–May 2, 2013.

J. M. SCAGLIONE, R. A. LEFEBVRE, G. RADULESCU, H. J. SMITH, D. ILAS, K. R. ROBB, and J. C. WAGNER, "Integrating Data and Analysis Capabilities for Cask-Specific Safety Evaluations," Proceedings of the 14th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 28–May 2, 2013.

A. M. IBRAHIM, P. WILSON, D. E. PEPLOW, S. W. MOSHER, M. SAWAN, J. C. WAGNER, and T. M. EVANS, "Automatic Mesh Adaptivity for CADIS and FW-CADIS Neutronics Modeling of Difficult Shielding Problems," Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2013), Sun Valley, ID, May 11–17, 2013.

A. M. IBRAHIM, D. E. PEPLOW, K. B. BEKAR, C. CELIK, D. ILAS, J. M. SCAGLIONE, and J. C. WAGNER, "Acceleration of Monte Carlo Fission Source Convergence Using Deterministic Starting Sources for Used Nuclear Fuel Cask-Specific Criticality Analysis," Proceedings of the Nuclear Criticality Safety Division 2013, Wilmington, NC, September 29–October 3, 2013.

T. M. MILLER et al., "Analysis of Measured Data from Experiments 2 and 3 of the 2010 Criticality Accident Alarm System Benchmark at the CEA Valduc Silene Facility," Proceedings of the Nuclear Criticality Safety Division 2013, Wilmington, NC, September 29–October 3, 2013.

J. C. WAGNER, J. CARTER, M. R. FELDMAN, R. L. HOWARD, M. NUTT, and J. WILLIAMS, "Overview of the Department of Energy's Nuclear Fuels Storage and Transportation Planning Project," Proceedings of the Institute of Nuclear Materials Management (INMM) - 55th Annual Meeting, Atlanta, GA, July 20–24, 2014.

J. C. WAGNER, J. CARTER, M. R. FELDMAN, R. L. HOWARD, M. NUTT and J. WILLIAMS, "Overview of the Department of Energy's Nuclear Fuels Storage and Transportation Planning Project," Proceedings of WM2015, Phoenix, AZ, March 15–19, 2015.

M. NUTT, J. C. WAGNER, M. R. FELDMAN, J. CARTER and R. HOWARD, "Nuclear Fuel Storage and Transportation Planning Project Strategic Crosscutting Activities," Proceedings of WM2015, Phoenix, AZ, March 15–19, 2015.

M. FELDMAN, J. WAGNER, K. CONNOLLY, S. MAHERAS, E. BICKFORD, J. JONES, and P. SCHWAB, "Laying the Groundwork for a Large-Scale Spent Nuclear Fuel Transportation System," Proceedings of WM2015 Conference, Phoenix, AZ, March 15–19, 2015.

M. R. FELDMAN, J. C. WAGNER, K. J. CONNOLLEY, J. WILLIAMS, E. BICKFORD, and J. JONES, "Laying the Groundwork for a Large-scale Used Fuel Transportation System," Proceedings of International High Level Radioactive Waste Management (IHLRWM) Conference, Charleston, SC, April 12–16, 2015.

V. SOBES, J. M. SCAGLIONE, J. C. WAGNER, and M. E. DUNN, "Validation Study for Crediting Chlorine in Criticality Analyses for Spent Nuclear Fuel Disposition," Proceedings of International Workshop on Operational and Regulatory Aspects of Criticality Safety, Albuquerque, NM, May 19–21, 2015.

K. BANERJEE, J. M. SCAGLIONE, J. C. WAGNER, and R. A. LEFEBVRE, "Criticality Safety Assessment for As-loaded Spent Fuel Storage and Transportation Casks," Proceedings of International Workshop on Operational and Regulatory Aspects of Criticality Safety, Albuquerque, NM, May 19–21, 2015.

T. M. MILLER, C. CIHANGIR, M. E. DUNN, J. C. WAGNER, K. L. MCMAHAN, N. AUTHIER, X. JACQUET, G. ROUSSEAU, H. WOLFF, J. PIOT, L. SAVANIER, N. BACLET, Y. LEE, V. MASSE, J. TRAMA, E. GAGNIER, S. NAURY, R. HUNTER, S. KIM, G. M. DULIK, and K. H. REYNOLDS, "Evaluation of the Concrete Shield Compositions from the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc Silene Facility," Proceedings of ICNC 2015, Charlotte, NC, September 13–17, 2015.

V. SOBES, J. M. SCAGLIONE, J. C. WAGNER, and M. E. DUNN, "Validation Study for Crediting Chlorine in Criticality Analyses for Spent Nuclear Fuel Disposition," Proceedings of ICNC 2015, Charlotte, NC, September 13–17, 2015.

Awards:

2013 Ernest Lawrence Award in Computer, Information, and Knowledge Sciences category, "For groundbreaking theory and development of consistent, accurate, and efficient Monte Carlo computational solutions of the Boltzmann transport equation over the complete domain, and for its broad application to complex real world radiation transport problems."

Department of Energy Special Recognition Award. "This award recognized your more than 2 years of service on this first of a kind project within the Office of Nuclear Energy. Your personal dedication in standing up the project, recruiting an outstanding team, and laying out plans for accomplishing work ... is a model for all National Technical Directors to emulate." (2014)

2014 Nuclear Engineering Outstanding Engineering Alumnus, The Pennsylvania State University College of Engineering's Highest Honor

Fellow of the American Nuclear Society, 2012

Research Interests:

Advanced reactor technologies and systems
Nuclear fuels and materials
Spent nuclear fuel management and disposition
Nuclear computational methods, including Monte Carlo, deterministic, hybrid radiation transport, and variance reduction methods

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