Stuart Arm
Stuart Arm
Biography
Stuart Arm, PhD, is a senior technical advisor who returned to Pacific Northwest National Laboratory (PNNL) in 2019 after twelve years working in industry. Dr. Arm holds a PhD in chemical engineering from Imperial College, London, and has thirty years of experience in national laboratories and the nuclear industry in the United Kingdom and United States. He establishes PNNL and Department of Energy strategic plans and objectives for radiochemical process flowsheets and technologies for treating and managing radioactive waste and commercial used nuclear fuel while acknowledging emerging national and international trends. Dr. Arm employs a collaborative and leading approach to technology and flowsheet maturation and integration to establish implementation strategies with multi-technical and organizational elements.
Dr. Arm is currently leader of the Nuclear Design Concepts and Integration team, part of the Experimental & Computational Engineering Group. As leader, he manages staff who use their mechanical and chemical engineering expertise to establish integrated design concepts for nuclear waste management and treatment plant.
Research Interest
- Nuclear fuel recycling
- Nuclear waste processing
- Liquid-liquid extraction
- Ion exchange
- Chemical process separations
- Management of technical and engineering organizations, programs, and projects
Disciplines and Skills
- Chemical Process Engineering
- Collaborative Style
- Flowsheet Development
- Leadership Skills
- Mentoring
- Negotiation
- Nuclear Fuel Cycle
- Nuclear Materials Processing
- Nuclear Waste Management
- Process Plants
- Process Development
- Program Coordination
- Radioactive Waste Management
- Radiochemical Processing
- Radiochemical Separations
- Strategic Business Direction
- Technology Leadership
- Waste Processing
Education
- PhD, Chemical Engineering, Imperial College London
- MEng, Chemical Engineering, Imperial College London
Affiliations and Professional Service
- Past Chair (2009), Current Senior Member, American Institute of Chemical Engineers, Nuclear Engineering Division
- American Nuclear Society
Publications
2023
- Arm S.T., S.D. Davidson, G.B. Hall, M.J. Iedema, A.P. Jivelekas, G.J. Lumetta, and R.M. Pratt, et al. 2023. Feasibility of Pulsed Current Technology for Removing Bulk Carbon from TRISO-based Fuels. PNNL-34412. Richland, WA: Pacific Northwest National Laboratory. Feasibility of Pulsed Current Technology for Removing Bulk Carbon from TRISO-based Fuels
- Ivanusa P., J.B. Clarity, and S.T. Arm. 2023. "Modeling Non-UO2 Fuel With UNF-ST&DARDS." In Transactions of the American Nuclear Society, 128, 91-94. Downers Grove, Illinois:American Nuclear Society. PNNL-SA-181629.
2020
- Arm S.T. 2020. Readiness Evaluation for Sustained Operations. PNNL-29926. Richland, WA: Pacific Northwest National Laboratory. Readiness Evaluation for Sustained Operations
- Arm S.T., D.E. Holcomb, R. Howard, and B.J. Riley. 2020. Status of Fast Spectrum Molten Salt Reactor Waste Management Practice. PNNL-30739. Richland, WA: Pacific Northwest National Laboratory. Status of Fast Spectrum Molten Salt Reactor Waste Management Practice
2008
- Fiskum S.K., S.T. Arm, M.J. Steele, and M.R. Thorson. 2008. "SPHERICAL RESORCINOL-FORMALDEHYDE PERFORMANCE TESTING WITH HANFORD TANK WASTE." Solvent Extraction and Ion Exchange 26, no. 4:435-452. PNNL-SA-56239. doi:10.1080/07366290802182691
- Kuhn W.L., S.T. Arm, J.L. Huckaby, D.E. Kurath, and S.D. Rassat. 2008. Technical Basis of Scaling Relationships for the Pretreatment Engineering Platform. PNNL-16948. Richland, WA: Pacific Northwest National Laboratory. Technical Basis of Scaling Relationships for the Pretreatment Engineering Platform
- Mahoney L.A., J.M. Alzheimer, S.T. Arm, C.E. Guzman-Leong, L.K. Jagoda, C.W. Stewart, and B.E. Wells, et al. 2008. "Large-Scale Testing of Effects of Anti-Foam Agent on Gas Holdup in Process Vessels in the Hanford Waste Treatment Plant - 8280." In Waste Management 2008 HLW, TRU, LLW/ILW, Mixed, Hazardous Wastes & Environmental Management. Tucson, Arizona: Arizona Board of Regents. PNNL-SA-58053.
- Stewart C.W., C.E. Guzman-Leong, S.T. Arm, M.G. Butcher, E.C. Golovich, L.K. Jagoda, and W.R. Park, et al. 2008. Results of Large-Scale Testing on Effects of Anti-Foam Agent on Gas Retention and Release. PNNL-17170. Richland, WA: Pacific Northwest National Laboratory. Results of Large-Scale Testing on Effects of Anti-Foam Agent on Gas Retention and Release
2007
- Arm S.T., A.P. Poloski, C.W. Stewart, P.A. Meyer, and D.E. Kurath. 2007. "Gas Generation and Hold-Up in Hanford Waste Treatment Plant Process Streams Containing Anti-Foam Agent (AFA)." In 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control and Management. Assessing the Safety and Technology of Nuclear Hydrogen Production, Control and Management on a Global Scale ST-NH2, Boston, Massachusetts, June 24-28, 2007, 6 pages. La Grange Park, Illinois: American Nuclear Society. PNNL-SA-54390.
- Arm S.T., G.J. Lumetta, and T.G. Levitskaia. 2007. "Flowsheet Modeling and Testing of Pseudohydroxide Extraction from Aqueous Sodium Hydroxide Solutions with 3,5-di-tert-Butylphenol in Isopar� L Modified with Exxal� 8." Solvent Extraction and Ion Exchange 25, no. 5:577-591. PNNL-SA-53233. doi:10.1080/07366290701512691
- Fiskum S.K., S.T. Arm, M.K. Edwards, M.J. Steele, and K.K. Thomas. 2007. Storage and Aging Effects on Spherical Resorcinol-Formaldehyde Resin Ion Exchange Performance. PNNL-16832. Richland, WA: Pacific Northwest National Laboratory. Storage and Aging Effects on Spherical Resorcinol-Formaldehyde Resin Ion Exchange Performance
2006
- Arm S.T., and J.A. Jenkins. 2006. "Haze Formation and Behavior in Liquid-Liquid Extraction Processes." In Separations for the Nuclear Fuel Cycle in the 21st Century, ACS Symposium Series, edited by Gregg J Lumetta, et al. 103-118. Washington, District Of Columbia: American Chemical Society. PNWD-SA-6586.
- Peterson R.A., S.K. Fiskum, S.T. Arm, and D.L. Blanchard. 2006. "Cesium Removal Demonstration Using Selected Actual Waste Samples from the Hanford Reservation Tank Farm." Separation Science and Technology 41, no. 11:2361-2371. PNWD-SA-7149.
2005
- Arm S.T., D.L. Blanchard, and S.K. Fiskum. 2005. "Chemical Degradation of an Ion Exchange Resin Processing Salt Solutions." Separation and Purification Technology 43, no. 1:59-69. PNWD-SA-6222. doi:10.1016/j.seppur.2004.10.001
- Fiskum S.K., D.L. Blanchard, S.T. Arm, and R.A. Peterson. 2005. "CESIUM REMOVAL FROM SIMULATED AND ACTUAL HANFORD TANK WASTE USING ION EXCHANGE." Separation Science and Technology 40, no. 1-3:51-67. PNWD-SA-6199. doi:10.1081/SS-200041760
2004
- Toth J.J., D.L. Blanchard, S.T. Arm, and M.W. Urie. 2004. "Partition Coefficients of Selected Compounds Using Ion Exchange Separation of Cesium From High Level Waste." In AIChE Spring National Meeting, Conference Proceedings, April 25-29, 2004, New Orleans, Louisiana, 2642-2651. New York, New York:American Institute of Chemical Engineers. PNNL-SA-41455.