PNNL

Safety engineer with supporting nuclear licensing, hazard and accident analyses and safety control development, system engineering, and project management. He has conducted hazards and safety analysis for petroleum systems and for U.S. Department of Energy (DOE) nuclear chemical facilities.

• Process Safety Management (PSM)
• Process Hazard Analysis
• Safety Analysis
• Control Development
• Risk Management
• Documented Safety Analysis

• Graduate Studies, Instrumentation and Control Systems, Idaho State University
• B.S., Engineering, Idaho State University, 1988

• Engineer-In-Training #3115, Idaho State Board of Professional Engineers

2024

• Coles G.A., T.A. Ikenberry, S.M. Short, M.S. Taylor, H.E. Adkins, P.P. Lowry, and C.A. Condon, et al. 2024. Development and Demonstration of a Risk Assessment Approach for Approval of a Transportation Package of a Transportable Nuclear Power Plant for Domestic Highway Shipment. PNNL-36380 Revision 1. Richland, WA: Pacific Northwest National Laboratory. Development and Demonstration of a Risk Assessment Approach for Approval of a Transportation Package of a Transportable Nuclear Power Plant for Domestic Highway Shipment
• Richmond D.J., K.M. Thomas, N.L. LaHaye, P.P. Lowry, J.B. Napier, S.M. Short, and D.R. Todd. 2024. Assessment of Technical Information Needs and Considerations for Front-End Activities for Molten Salt Fuel Types. PNNL-33899 Rev. 1. Richland, WA: Pacific Northwest National Laboratory. Assessment of Technical Information Needs and Considerations for Front-End Activities for Molten Salt Fuel Types

2022

• Coles G.A., P.P. Lowry, J.R. Phillips, S.M. Short, C.A. Condon, S.J. Maheras, and T.A. Ikenberry, et al. 2022. Parametric Study of Factors that Affect Calculated Dose from TRISO Fueled Microreactor Transportation Accident. PNNL-33607. Richland, WA: Pacific Northwest National Laboratory. Parametric Study of Factors that Affect Calculated Dose from TRISO Fueled Microreactor Transportation Accident

2021

• Maheras S.J., G.A. Coles, J.R. Phillips, C.A. Condon, S.M. Short, H.E. Adkins, and P.P. Lowry, et al. 2021. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment. PNNL-33524. Richland, WA: Pacific Northwest National Laboratory. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment

2013

• Petti D.A., D.A. Petti, R.R. Hobbins, P.P. Lowry, and H. Gougar. 2013. "REPRESENTATIVE SOURCE TERMS AND THE INFLUENCE OF REACTOR ATTRIBUTES ON FUNCTIONAL CONTAINMENT IN MODULAR HIGH-TEMPERATURE GAS-COOLED REACTORS." Nuclear Technology 184, no. 2:181-197. PNNL-SA-99842.
• Unwin S.D., K.I. Johnson, W.J. Ivans, and P.P. Lowry. 2013. "A PROPOSED METHOD FOR ESTIMATING FAILURE RATES OF DEGRADED PASSIVE COMPONENTS IN THE NRC SIGNIFICANCE DETERMINATION PROCESS." Transactions of the American Nuclear Society 109, no. 1:2049-2050. PNNL-SA-99179.

2012

• Unwin S.D., P.P. Lowry, and M.Y. Toyooka. 2012. "RELIABILITY MODELS OF AGING PASSIVE COMPONENTS INFORMED BY MATERIALS DEGRADATION METRICS TO SUPPORT LONG-TERM REACTOR OPERATIONS." Nuclear Science and Engineering 171, no. 1:69-77. PNNL-SA-78802.
• Unwin S.D., R.F. Layton, K.I. Johnson, and P.P. Lowry. 2012. "Physics-Based Multi-State Models of Passive Component Degradation for the R7 Reactor Simulation Environment." In 11th International Probabilistic Safety Assessment and Management Conference and the Annual European Safety and Reliability Conference (PSAM11 ESREL 2012), June 25-29, 3012, Helsinki, Finland, 3, 1761-1770. Red Hook, New York:Curran Associates, Inc. PNNL-SA-85623.

2011

• Unwin S.D., P.P. Lowry, and M.Y. Toyooka. 2011. "A Methodology Supporting the Risk-Informed Management of Materials Degradation." In Proceedings of the 2011 American Nuclear Society Winter Meeting and Nuclear Technology Expo, October 30-November 3, 2011, Washington DC. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-80413.
• Unwin S.D., P.P. Lowry, M.Y. Toyooka, and B.E. Ford. 2011. "DEGRADATION SUSCEPTIBILITY METRICS AS THE BASES FOR BAYESIAN RELIABILITY MODELS OF AGING PASSIVE COMPONENTS AND LONG-TERM REACTOR RISK." In Proceedings of the ASME 2011 Pressure Vessels & Piping Conference (PVP2011), July 17-21, 2011, Baltimore, Maryland, Paper No. PVP2011-58073. New York, New York:ASME. PNNL-SA-78798.
• Unwin S.D., P.P. Lowry, R.F. Layton, P.G. Heasler, and M.B. Toloczko. 2011. "Multi-State Physics Models of Aging Passive Components in Probabilistic Risk Assessment." In International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2011), March 13-17, 2011, Wilmington, North Carolina, 1, 161-172. La Grange Park, Illinois:Amercian Nuclear Society. PNNL-SA-76893.

2010

• Unwin S.D., P.P. Lowry, and M.Y. Toyooka. 2010. "A New Class of Risk-Importance Measures to Support Reactor Aging Management and the Prioritization of Materials Degradation Research." In 10th International Probabilistic Safety Assessment & Management Conference - PSAM10, June 7-11, 2010, Seattle, WA. Mannheim:International Association for Probabalistic Safety Assessment & Management (IAPSAM). PNNL-SA-70455.
• Unwin S.D., P.P. Lowry, and M.Y. Toyooka. 2010. "COMPONENT DEGRADATION SUSCEPTIBILITIES AS THE BASES FOR MODELING REACTOR AGING RISK." In 2010 Pressure Vessels & Piping Conference (PVP 2010): Pressure Vessel Technology for Energy Challenge, Paper No. PVP2010-25750. New York, New York:American Society of Mechanical Engineers. PNNL-SA-71292.

2009

• Unwin S.D., P.P. Lowry, and M.Y. Toyooka. 2009. "Informing Reactor Aging Management by Extended Risk Methodology." Transactions of the American Nuclear Society 101, no. 1:1047-1048. PNNL-SA-66915.