PNNL

Brady Hanson has more than three decades of experience in the nuclear energy field and industry. He joined PNNL in 1998 as a senior research scientist and was promoted to staff scientist in 2005; he currently leads experiments as principal investigator for the Spent Fuel and Waste Science and Technology campaign for the U.S. Department of Energy’s Office of Nuclear Energy.

Hanson served as an adjunct professor at the University of Missouri from 2006 – 2012, and he’s mentored numerous students at PNNL.

• PhD in Nuclear Engineering, University of California, Berkeley, 1998
  Dissertation: “The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation” 
• ME in Nuclear Engineering, University of California, Berkeley, 1997
  Thesis: “Development and Testing of a Computer Code to Model Resonance Absorption in Nuclear Fuel: Distribution Profiles of Actinides and Fission Products”
• BS in Chemical Engineering, Brigham Young University, 1990

• Co-Chair, Technical Program for the International High Level Radioactive Waste Management Conference, American Nuclear Society (ANS) (2017)
• Committee Member and Session Organizer, Technical Program for all Engineered Barrier Systems Sessions, International High Level Radioactive Waste Management Conference, ANS (2008, 2013, 2015)
• Meeting Leader, C26.13 Meetings in Vienna, Austria, ASTM International (2016)
• Meeting Leader, C26.13 Meetings in Avignon, France, ASTM International (2013)
• Co-Chair, 24^th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle, ASTM International (2008)
• Task Group Chair, Light Water Reactor Fuels Task Group, within Committee C26.13 responsible for C1562, Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
• Task Group Chair, Spent Fuel Dissolution Task Group, within Committee C26.13, ASTM International
• Task Group Member, responsible for C1553, Standard Guide for Drying Behavior of Spent Nuclear Fuel
• Member, C26.02 Fuel and Fertile Material Specifications, ASTM International
• Member, International Expert Group on Assay Data of Spent Nuclear Fuel, Organization for Economic Co-Operation and Development (OECD)/Nuclear Energy Agency

• Fitzner/Eberhardt Award for Outstanding Contributions to Science and Engineering Education Nominee, PNNL (2007)

2023

Shimskey R.W., J.R. Allred, S.E. Asmussen, S.K. Cooley, R.C. Daniel, L.H. Dinh, and M.K. Edwards, et al. 2022. PNNL FY2021 Sibling Pin Testing Results. PNNL-32783. Richland, WA: Pacific Northwest National Laboratory. PNNL FY2021 Sibling Pin Testing Results

2022

Casella A.M., M.S. Lanza, B.D. Hanson, S. Durbin, and J. Philips. 2022. "Characterization of the Aerosol Source Term in Dry Storage Canisters." In International High-Level Radioactive Waste Management Conference, November 13-17, 2022, Phoenix, AZ, 412-416. Downers Grove, Illinois: American Nuclear Society. PNNL-SA-174498.

2021

Scheele R.D., B.D. Hanson, and A.M. Casella. 2021. "Effect of Added Gadolinium Oxide on the Thermal Air Oxidation of Uranium Dioxide." Journal of Nuclear Materials 552. PNNL-SA-158705. doi:10.1016/j.jnucmat.2021.153008

Suffield S.R., J.A. Fort, P.J. Jensen, W.A. Perkins, B.J. Jensen, C.L. Grant, and R. Ekre, et al. 2021. Thermal and Deposition Modeling of the Canister Deposition Field Demonstration. PNNL-31882. Richland, WA: Pacific Northwest National Laboratory. Thermal and Deposition Modeling of the Canister Deposition Field Demonstration

2020

Buck E.C., R.S. Wittman, and B.D. Hanson. 2020. Independent Technical Review of INL Aluminum-Clad Spent Nuclear Fuel (ASNF) Oxide Layer Radiolytic Gas Generation Resolution: Task 2. PNNL-30701. Richland, WA: Pacific Northwest National Laboratory. Independent Technical Review of INL Aluminum-Clad Spent Nuclear Fuel (ASNF) Oxide Layer Radiolytic Gas Generation Resolution: Task 2

2019

Klymyshyn N.A., P. Ivanusa, K. Kadooka, C.J. Spitz, E.D. Irick, P.J. Jensen, and S.B. Ross, et al. 2019. Structural Dynamic Analysis of Spent Nuclear Fuel. PNNL-29150. Richland, WA: Pacific Northwest National Laboratory. Structural Dynamic Analysis of Spent Nuclear Fuel

2016

Shimskey R.W., P.J. Jensen, P.J. MacFarlan, L. Lin, and B.D. Hanson. 2016. "Mechanical Testing of Hydrided Fuel Cladding." In Light Water Reactor (LWR) Fuels with Enhanced Safety and Performance Meeting (Top Fuel 2016), September 11-15, 2016, Boise ID, 1, 563-572. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-117815.

Ross SB, RE Best, PJ Jensen, NA Klymyshyn, BD Hanson, P McConnell, SJ Saltzstein, KB Sorenson, W Shust, D Garrido, R Walker, S Gurule, and R Pena. 2016. ENSA/DOE Transport Shock and Vibration Test Plan. PNNL-25723, Pacific Northwest National Laboratory, Richland, WA.

Hanson BD. 2016. "High Burnup Spent Fuel Data Project." Invited Speaker at Nuclear Waste Technical Review Board Meeting, Knoxville, TN on February 17, 2016. PNNL-SA-115866.

Hanson BD. 2016. "High Burnup Fuel, Associated Data Gaps, and Integrated Approach for Addressing the Gaps." Invited Speaker at Nuclear Waste Technical Review Board Meeting, Knoxville, TN on February 17, 2016. PNNL-SA-115865.

Casella AJ, BD Hanson, and WH Miller. 2016. "The effect of fuel chemistry on UO2 dissolution." Journal of Nuclear Materials 476:45-55.

Hanson BD, S Marschman, MC Billone, JM Scaglione, KB Sorenson, and SJ Saltzstein. 2016. High Burnup Spent Fuel Data Project Sister Rod Test Plan Overview. PNNL-25374, Pacific Northwest National Laboratory, Richland, WA.

2015

Meyer RM, JM Cuta, AM Jones, KM Denslow, P Ramuhalli, HE Adkins, Jr, and BD Hanson. 2015. "FEASIBILITY OF ACOUSTIC METHODS FOR IMPURITY GAS MONITORING IN DRY STORAGE SYSTEMS." In 15th International High-Level Radioactive Waste Management Conference, April 12-16, 2015, Charleston, South Carolina, pp.  829-834.  American Nuclear Society, LaGrange Park, IL.

Jensen PJ, DJ Sunderland, SB Ross, RO Montgomery, BD Hanson, and R Devanathan. 2015. "Gap Analysis to Support Modeling the Long-Term Degradation of Used Nuclear Fuel Canisters." In International High-Level Radioactive Waste Management: Real World Solutions for Integrated Management of Used Fuel and HLW, April 12-16, 2015, Charleston, South Carolina.  American Nuclear Society, La Grange Park, IL.

2014

Wittman RS, and BD Hanson. 2014. "Radiolysis Model Analysis for a Used Fuel Storage Canister." In Proceedings of the International High-Level Radioactive Waste Management Conference. PNNL-SA-107134, Pacific Northwest National Laboratory, Richland, WA. 

Klymyshyn NA, PJ Jensen, SE Sanborn, and BD Hanson. 2014. FUEL ASSEMBLY SHAKER AND TRUCK TEST SIMULATION. PNNL-23688, Pacific Northwest National Laboratory, Richland, WA.

Klymyshyn NA, NK Karri, HE Adkins, Jr, and BD Hanson. 2014. STRUCTURAL UNCERTAINTY OF USED NUCLEAR FUEL IN DRY STORAGE CANISTERS. PNNL-23710, Pacific Northwest National Laboratory, Richland, WA.

Casella AM, SK Loyalka, and BD Hanson. 2014. "Modeling of Particulate Behavior in Pinhole Breaches." Nuclear Technology 186(1):99-114.

2013

Meyer R M, Hanson B D, Sorenson K B. 2013. "A Review of NDE Methods for Detecting and Monitoring of Atmospheric SCC in Dry Cask Storage Canisters for Used Nuclear Fuel" Corrosion 2013 Conference and Expo, March 17-21, 2013, Orlando, Florida.

Sorenson K B, Hanson B D. 2013. "Making the Case For Safe Storage of Used Nuclear Fuel For Extended Periods of Time: Combining Near-Term Experiments and Analyses with Longer-Term Confirmatory Demonstrations" Nuclear Engineering and Technology 45(4):421-426.

Hanson BD, RW Shimskey, CA Lavender, PJ MacFarlan, and PW Eslinger. 2013. Hydride Rim Formation in Unirradiated Zircaloy. PNNL-22438, Pacific Northwest National Laboratory, Richland, WA.

2012

Klymyshyn N A, Adkins H E, Hanson B D. 2012. "ASSESSING MATERIAL DEGRADATION EFFECTS ON LONG TERM STORAGE STRUCTURAL ANALYSES" 2013 International High-Level Radioactive Waste Management Conference (American Nuclear Society).

Hanson BD, A Alsaed, CT Stockman, and KB Sorenson. 2012. "U.S. Gap Analysis to Support Extended Storage of Used Nuclear Fuel."  In PSAM 11 & ESREL 2012, Helsinki, Finland. PNNL-SA-87194.

Hanson BD.  2012. "DOE-NE Plans for Cladding R&D."  Invited Speaker at NEI Used Fuel Management Conference, St. Petersburg, FL on May 10, 2012.  PNNL-SA-87635. 

Hanson BD, AM Johnsen, BA Collins, PP Schonewill, MC Brady Raap, and GL Swearingen. 2012. FY10 Summary Report Augmentation of International Spent Fuel Databases.  PNNL-21469, Pacific Northwest National Laboratory, Richland, WA. 

Crawford SL, AD Cinson, PJ MacFarlan, BD Hanson, and R Mathews.  2012. Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation. PNNL-21547; NUREG/CR-7142, Pacific Northwest National Laboratory, Richland, WA. 

Hanson, BD, CT Stockman, and H Alsaed.  Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses.  FCRD-USED-2012-0002159, PNNL-21596. 2012.

Hanson, BD, H Alsaed, and CT Stockman.  Used Nuclear Fuel Storage and Transportation Data Gap Prioritization.  FCRD-USED-2012-000109, PNNL-21360. 2012.

2011

McConnell P, BD Hanson, M Lee, and KB Sorenson. 2011. "Extended Dry Storage of Used Nuclear Fuel: Technical Issues: A USA Perspective." Nuclear Engineering and Technology 43(5):405-412. 

Hanson, BD et al. September 22, 2011. Infrastructure Capabilities Needed to Support R&D for Extended Storage.

Hanson, BD, H Alsaed, CT Stockman, DG Enos, R Meyer, and KB Sorenson.  Gap Analysis to Support Extended Storage of Used Nuclear Fuel.  FCRD-USED-2011-000136, PNNL-20509

Cinson AD, SL Crawford, PJ MacFarlan, R Mathews, BD Hanson, and AA Diaz.  2011.  "Ultrasonic Phased Array Evaluation of Control Rod Drive Mechanism (CRDM) Nozzle Interference Fit and Weld Region."  In ASME 2011 Pressure Vessels and Piping Conference. 

Soderquist CZ, AM Johnsen, BK McNamara, BD Hanson, JW Chenault, KJ Carson, and SM Peper. 2011. “Dissolution of Irradiated Commercial UO₂ Fuels in Ammonium Carbonate and Hydrogen Peroxide”.  Industrial and Engineering Chemistry Research 50(4)1813-1818.

2010

Soderquist CZ, and BD Hanson.  2010. “Dissolution of Spent Nuclear Fuel in Carbonate-Peroxide Solution”.  Journal of Nuclear Materials 396(2-3)159-162.

Daniel RC, JM Billing, JR Bontha, CF Brown, PW Eslinger, BD Hanson, JL Huckaby, NK Karri, ML Kimura, DE Kurath.  2010.  EFRT M-12 Issue Resolution:  Comparison of Filter Performance at PEP and CUF Scale, WTP-RPT-185 Rev. 1, Pacific Northwest National Laboratory, Richland, WA.

Mahoney LA, SD Rassat, PW Eslinger, RL Aaberg, PM Aker, EC Golovich, BD Hanson, T Hausmann, JL Huckaby, DE Kurath, SK Sundaram, ST Yokuda.  2010.  EFRT M-12 Issue Resolution:  Caustic Leach Rate Constants from PEP and Lab-Scale Tests, WTP-RPT-186 Rev 1, Pacific Northwest National Laboratory, Richland, WA.

Baldwin DL, PP Schonewill, JJ Toth, JL Huckaby, PW Eslinger, BD Hanson, DE Kurath.  2010.  EFRT M-12 Issue Resolution:  Solids Washing, WTP-RPT-187 Rev 1, Pacific Northwest National Laboratory, Richland, WA.

Rapko BM, CF Brown, PW Eslinger, MS Fountain, BD Hanson, TS Hausmann, JL Huckaby, DE Kurath.  2010.  EFRT M-12 Issue Resolution:  Comparison of PEP and Bench-Scale Oxidative Leaching Results, WTP-RPT-188 Rev 1, Pacific Northwest National Laboratory, Richland, WA.

2009

Kurath DE, BD Hanson, MJ Minette, DL Baldwin, BM Rapko, LA Mahoney, PP Schonewill, RC Daniel, PW Eslinger, JL Huckaby, JM Billing, PS Sundar, GB Josephson, JJ Toth, ST Yokuda, EBK Baer, SM Barnes, EC Golovich, SD Rassat, CF Brown, JGH Geeting, GJ Sevigny, AJ Casella, JR Bontha, RL Aaberg, PM Aker, CE Guzman-Leong, ML Kimura, SK Sundaram, RP Pires, BE Wells, and OP Bredt.  2009.  Pretreatment Engineering Platform Phase 1 Final Test Report, WTP-RPT-197, Rev 0, Pacific Northwest National Laboratory, Richland, WA.

Daniel RC, JM Billing, JR Bontha, CF Brown, PW Eslinger, BD Hanson, JL Huckaby, NK Karri, ML Kimura, DE Kurath.  August 2009.  EFRT M-12 Issue Resolution:  Comparison of Filter Performance at PEP and CUF Scale, WTP-RPT-185, Pacific Northwest National Laboratory, Richland, WA.

Mahoney LA, SD Rassat, PW Eslinger, RL Aaberg, PM Aker, EC Golovich, BD Hanson, T Hausmann, JL Huckaby, DE Kurath, SK Sundaram, ST Yokuda.  August 2009.  EFRT M-12 Issue Resolution:  Caustic Leach Rate Constants from PEP and Lab-Scale Tests, WTP-RPT-186, Pacific Northwest National Laboratory, Richland, WA.

Baldwin DL, PP Schonewill, JJ Toth, JL Huckaby, PW Eslinger, BD Hanson, DE Kurath.  August 2009.  EFRT M-12 Issue Resolution:  Solids Washing, WTP-RPT-187, Pacific Northwest National Laboratory, Richland, WA.

Rapko BM, CF Brown, PW Eslinger, MS Fountain, BD Hanson, TS Hausmann, JL Huckaby, DE Kurath. August 2009.  EFRT M-12 Issue Resolution:  Comparison of PEP and Bench-Scale Oxidative Leaching Results, WTP-RPT-188, Pacific Northwest National Laboratory, Richland, WA.

Hanson BD, AM Casella, and CE Beyer.  2009.  "The RADFUEL Concept to Accelerate Fuel Qualification."  In Transactions of the American Nuclear Society 2009 Winter Meeting.  American Nuclear Society, La Grange Park, IL.

Casella AM, BD Hanson, and PJ MacFarlan. 2009. "Progress in Fuel Pellet Fabrication and Thermo-Physical Analysis at PNNL."   In Transactions of the American Nuclear Society 2009 Winter Meeting.  American Nuclear Society, La Grange Park, IL.

Casella AJ, BD Hanson, and WH Miller.  2009. "Fuel Matrix Chemistry Effects on UO2 Dissolution."  InTransactions of the American Nuclear Society 2009 Winter Meeting. American Nuclear Society, La Grange Park, IL.

Johnsen AM, JM Billing, BD Hanson, GJ Lumetta, AJ Casella, SA Bryan, and TG Levitskaia. 2009. "Counter-Current Solvent Extraction Behavior of Neptunium." Abstract submitted to Sixteenth Symposium on Separation Science and Technology for Energy Applications.  PNNL-SA-67424.

Johnsen AM, CZ Soderquist, BD Hanson, BK Mcnamara, and SM Peper.  2009.  "A Simplified and Environmentally Benign Spent Nuclear Fuel Dissolution Process."  Abstract submitted to Sixteenth Symposium on Separation Science and Technology for Energy Applications.  PNNL-SA-67634.

Casella AM, BD Hanson, and SK Loyalka. 2009. "Computation of Free Molecular Flow in Nuclear Materials."  Journal of Nuclear Materials 394(2-3)123-130.

2008

Hanson BD, 2008.  Pretreatment Engineering Platform Data Analysis and Reporting Guidance, PNNL-SA-61630, Pacific Northwest National Laboratory, Richland, WA.

Hanson BD, RC Daniel, AM Casella, RS Wittman, W. Wu, PJ MacFarlan, RW Shimskey, Fuel-In-Air FY07 Summary Report, PNNL-17275, Rev. 1, Pacific Northwest National Laboratory, Richland, WA, September 2008.

Hanson BD. 2008. "Examining the Conservatisms in Dissolution Rates of Commercial Spent Nuclear Fuel."  In Proceedings of the 2008 International High-Level Radioactive Waste Management Conference American Nuclear Society, La Grange Park, IL. 

Casella AJ, BD Hanson, and WH Miller. 2008. "Factors Affecting UO2 Dissolution Under Geologic Disposal Conditions." In 2008 International High-Level Radioactive Waste Management. American Nuclear Society, La Grange Park, IL. 

Friese JI, M Douglas, BD Hanson, RF Payne, and MK Edwards.  2008.  "Neptunium Thermodynamics in a Geological Repository for Spent Nuclear Fuel." In 2008 International High-Level Radioactive Waste Management.  American Nuclear Society, La Grange Park, IL. 

Kline AJ, BD Hanson, and WH Miller.  2008.  "The Temperature, Oxygen, and Fuel Chemistry Dependence of UO2 Dissolution Under Repository Conditions."  In Transactions of the American Nuclear Society 2008 Annual Meeting.  American Nuclear Society, La Grange Park, IL.

Lumetta GJ, JM Billing, SA Bryan, BD Hanson, and TG Levitskaia.  2008.  "Integration of Counter-Current Solvent Extraction Testing Capability with New Online Monitoring Tools."  32nd Annual Actinide Separations Conference, Park City, UT. 

2007

Casella AM, SK Loyalka, and BD Hanson. 2007. "Monte Carlo Modeling of Molecular Flow through Nano-Pathways in Irradiated TRISO Fuels." In American Nuclear Society 2007 Winter Meeting Proceedings. American Nuclear Society, La Grange Park, IL.

Casella AM, SK Loyalka, and BD Hanson. 2007. "A Monte Carlo Program for Modeling Particulate Flow through Pinhole Breaches in Spent Fuel Canisters." In American Nuclear Society Winter 2007 Meeting Proceedings. American Nuclear Society, La Grange Park, IL.

Casella AM, SK Loyalka, and BD Hanson. 2007. "Pinhole Breaches in Spent Fuel Containers: Improvements to Conservative Models of Aerosol Release and Plugging." In American Nuclear Society 2007 Winter Meeting Proceedings. American Nuclear Society, La Grange Park, IL.

Kline AJ, BD Hanson, and WH Miller. 2007. "Characteristics of UO2 Dissolution as Determined by SPFT Tests." In American Nuclear Society 2007 Winter Meeting Proceedings. American Nuclear Society, La Grange Park, IL.

2006

Abrefah J, CH Delegard, BD Hanson, and PA Scott. 2006.  Battelle Peer Review of Nexia Solutions Report "International Spent Fuel Management Study”. PNWD-3748, Battelle—Pacific Northwest Division, Richland, WA.

Casella AM, SK Loyalka, and BD Hanson. 2006. "Plugging Effects on Depressurization Time in Dry Storage Containers with Pinhole Breaches."  In Transactions of the American Nuclear Society Winter 2006 Meeting, vol. 95, ed. Christine A. Yoelin, Julie B. Rule, pp. 209-210. American Nuclear Society, La Grange Park, IL. 

Kline AJ, BD Hanson, WH Miller, and R Wittman. 2006. "Modeling the Radiolysis Effect on CSNF Dissolution Kinetics." In Transactions of the American Nuclear Society Winter Meeting (2006), vol. 95, pp. 177-178. American Nuclear Society, La Grange Park, IL. 

Casella AM, SK Loyalka, and BD Hanson. 2006. "Pinhole Breaches in Spent Fuel Containers: Some Modeling Considerations."  In 2006 ANS Annual Meeting, Reno Nevada, June 4-8, 2006. Published in Transactions of the American Nuclear Society, vol. 94, pp. 80-81. American Nuclear Society, La Grange Park, IL. 

Miller WH, AJ Kline, and BD Hanson. 2006. "Dosimetry Modeling for Predicting Radiolytic Production at the Spent Fuel - Water Interface." In 11th International High-Level Radioactive Waste Management Conference (IHLRWM), pp. 698-711.  American Nuclear Society, Las Vegas, NV. 

Hanson BD, RS Wittman, AM Casella, J Abrefah, and SE Cumblidge.  2006.  "Modeling to Support Advanced Hybrid Fuels for Transmutation."  In Inert Matrix Fuel Workshop (IMF-11) October 10-12, 2006.  PNNL-SA-50850, Pacific Northwest National Laboratory, Richland, WA. 

Hanson BD.  2006.  "CSNF Dissolution Mechanisms and Rates." Presented by Brady D. Hanson (Invited Speaker) at NWTRB Fact Finding Meeting on Source Term, Las Vegas, NV on June 9, 2006.  PNNL-SA-50402. 

Hanson BD, WH Miller, and AJ Kline.  2006.  "Dissolution Mechanisms and Rates."  Presented by Brady D. Hanson, William H. Miller, Amanda J. Kline (Invited Speaker) at OST&I Source Term Program Review Meeting, Las Vegas, NV on March 14, 2006.  PNNL-SA-49005. 

2005

BD Hanson, “Flowthrough Dissolution of CSNF under Oxidizing Conditions”, presented at the DOE/CEA Technical Meeting, Las Vegas, NV, February 9, 2005.

BD Hanson, “Dry Air Oxidation of Commercial Spent Nuclear Fuel”, presented at the DOE/CEA Technical Meeting, Las Vegas, NV, February 8, 2005.

Douglas M, SB Clark, JI Friese, BW Arey, EC Buck, and BD Hanson. 2005. "Neptunium(V) Partitioning to Uranium(VI) Oxide and Peroxide Solids." Environmental Science and Technology 39(11):4117-4124.  

Douglas M, SB Clark, JI Friese, BW Arey, EC Buck, BD Hanson, S Utsunomiya, and RC Ewing. 2005. "Microscale Characterization of Uranium(VI) Silicate Solids and Associated Neptunium(V)." Radiochimica Acta 93(5):265-272.

Hanson BD, BK McNamara, EC Buck, JI Friese, ED Jenson, KM Krupka, and BW Arey. 2005. "Corrosion of commercial spent nuclear fuel. 1. Formation of studtite and metastudtite." Radiochimica Acta 93:159-168.

McNamara BK, BD Hanson, EC Buck, and CZ Soderquist. 2005. "Corrosion of Commercial Spent Nuclear Fuel. 2. A Radiochemical Analyses of Metastudtite and Leachates." Radiochimica Acta 93(3):169-175.

Wittman RS, EC Buck, and BD Hanson. 2005. Data Analysis of Plutonium Sorption on Colloids in a Minimal Kinetics Model. PNNL-15285, Pacific Northwest National Laboratory, Richland, WA.

2004 

Buck EC, BD Hanson, and BK McNamara. 2004. "The Geochemical Behaviour of Tc, Np, and Pu in Spent Nuclear Fuel in an Oxidizing Environment." Chapter 3 in Energy, Waste, and the Environment: A Geochemical Perspective, vol. 236, ed. R. Giere and P. Stille, pp. 65-88.  Geological Society, London, United Kingdom.

Buck EC, BD Hanson, JI Friese, M Douglas, and BK McNamara. 2004. "Evidence for Neptunium Incorporation into Uranium (VI) Phases." In Scientific Basis for Nuclear Waste Management XXVIII. Materials Research Society Symposium Proceedings, vol. 824, pp. 133-138.  Materials Research Society, Warrendale, PA. 

Buck EC, BK McNamara, and BD Hanson. 2004. Alternative Conceptual Model for Colloid Generation from Commercial Spent Nuclear Fuel. PNNL-14306, Pacific Northwest National Laboratory, Richland, WA.

Friese JI, M Douglas, BK McNamara, SB Clark, and BD Hanson. 2004. Np Behavior in Synthesized Uranyl Phases: Results of Initial Tests. PNNL-14856, Pacific Northwest National Laboratory, Richland, WA.

Hanson BD, and RB Stout. 2004. "Reexamining the Dissolution of Spent Fuel: A Comparison of Different Methods for Calculating Rates." In Scientific Basis for Nuclear Waste Management XXVIII. Materials Research Society Symposium Proceedings, vol. 824, pp. 89-94.  Materials Research Society, Warrendale, PA.

Hanson BD, JI Friese, and CZ Soderquist. 2004. "Initial Results from Dissolution Testing of Spent Fuel under Acidic Conditions." In Scientific Basis for Nuclear Waste Management XXVIII. Materials Research Society Symposium Proceedings, vol. 824, pp. 113-118.  Materials Research Society, Warrendale, PA.

McNamara BK, BD Hanson, EC Buck, and CZ Soderquist. 2004. "A radiochemical analyses of metastudtite and leachates from spent fuel." In Scientific Basis for Nuclear Waste Management XXVII. Materials Research Society Symposium Proceedings, vol. 824, pp. 139-144.  Materials Research Society, Warrendale, PA.

Scheele RD, BD Hanson, SE Cumblidge, ED Jenson, AE Kozelisky, RL Sell, PJ MacFarlan, and LA Snow. 2004. "Effect of Gadolinium Doping on the Air Oxidation of Uranium Dioxide." In Scientific Basis for Nuclear Waste Management XXVIII. Materials Research Society Symposium Proceeding, vol. 824, pp. 211-216.  Materials Research Society, Warrendale, PA.

Friese JI, M Douglas, E C Buck, S B Clark, B D Hanson.  “Neptunium incorporation/sorption with uranium alteration products.”  Presented and accepted for publication in Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Spring Meeting, April 12-16, 2004 San Francisco, CA.

Hanson BD, E.C. Buck, J.I. Friese, E.D. Jenson.  “The Effective Surface Area of Bare Spent Fuel for Dissolution:  The Effect of Less-Soluble Fission Products and Actinides.”  Presented at Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Spring Meeting, April 12-16, 2004 San Francisco, CA.

Buck EC, B. K. McNamara, and B. D. Hanson.  “Partitioning of Uranyl Oxide Hydrate Colloids at Air-Water Interfaces.”  Presented at Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Spring Meeting, April 12-16, 2004 San Francisco, CA.

2003

Buck EC, BK McNamara, M Douglas, and BD Hanson. 2003. Possible Incorporation of Neptunium in Uranyl (VI) Alteration Phases. PNNL-14277, Pacific Northwest National Laboratory, Richland, WA. 

Friese JI, EC Buck, BK McNamara, BD Hanson, and SC Marschman. 2003. Existing Evidence for the Fate of Neptunium in the Yucca Mountain Repository. PNNL-14307, Pacific Northwest National Laboratory, Richland, WA. 

McNamara BK, EC Buck, and BD Hanson. 2003. "Observation of Studtite and Metastudtite on Spent Fuel." In Scientific Basis for Nuclear Waste Management XXVI. Materials Research Society Symposium Proceedings, vol. 757, pp. 401-406.  Materials Research Society, Warrendale, PA.

McNamara BK, EC Buck, and BD Hanson.  2003.  "Fission product aggregation and flotation at the air-solution interface ."  Presented by Mcnamara, Bruce at 227th ACS National Meeting, March 28 - April 1, 2004, Anaheim, CA, Anaheim, CO on March 28, 2003.  PNNL-SA-41354, Pacific Northwest National Laboratory, Richland, WA.

Hanson BD, SE Cumblidge, RD Scheele, and RL Sell. "The Effect of Rare Earth Dopants on UO2 Oxidation." In Transactions American Nuclear Society, Vol. 88, pp. 414-415, June 1-5, 2003, San Diego, CA.

Friese JI, BD Hanson, EC Buck, and BK McNamara, “Partitioning of neptunium in spent nuclear fuel tests.”  Presented at the Actinide Separations Conference, Argonne, IL, June 12, 2003.

1999

“Spent Fuel Oxidation:  Effects of High-Burnup and Hydrated Phases and Preliminary Clad Unzipping Model,” presented at the International Spent Fuel Workshop, Toronto, Ontario, Canada, September 21-23, 1999.

“Spent Fuel Oxidation Activities,” presented to staff of Studsvik Nuclear AB (Sweden), Pacific Northwest National Laboratory, September 1999.

“Commercial Spent Fuel Tests at PNNL,” presented at the Container Lifetime Source-Term Appendix 7 Meeting (NRC/DOE), Lawrence Livermore National Laboratory, July 7-8, 1999.

“Spent Fuel Oxidation Testing at PNNL,” presented to members of the French Atomic Energy Commission at Pacific Northwest National Laboratory, March 1999.

1998

E.J. Kansa, B.D. Hanson, and R.B. Stout, “Grain Size and Burnup Dependence of Spent Fuel Oxidation:  Geological Repository Impact,” presented at the MRS meeting, Boston, MA, November 30-December 4, 1998.  Also printed as UCRL-JC-131592, Lawrence Livermore National Laboratory, October 1998.

Hanson BD, “The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation,” PNNL-11929, Pacific Northwest National Laboratory, Richland, WA, July 1998.

“The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation,” presented at the International Spent Fuel Workshop, Las Vegas, NV, May 18-20, 1998.

“Spent Fuel Oxidation Studies,” presented at the Geologic Disposal Support Project Program Review conducted by the Yucca Mountain Project M&O, Pacific Northwest National Laboratory, April 1998.

1994

“The Oxidation of Spent Fuel Using a Thermogravimetric Analysis (TGA) System,” presented at Spent Fuel Workshop 1994, Montebello, Quebec, Canada, August 22-24, 1994.

1993

Ludwig SB, G.E. Michaels, and B.D. Hanson, “Effects of Actinide Compositional Variability in the U.S. Spent Fuel Inventory on Partitioning-Transmutation Systems,” Proceedings of the International Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Argonne, Illinois, November 11-13, 1992, pp. 384-396 (1993).