PNNL

Pavlo Ivanusa is a nuclear engineer who joined Pacific Northwest National Laboratory (PNNL) in 2016. He currently works with the Applied Engineering team in the Earth Systems Sciences Division. Before this, he was with PNNL’s Risk and Decision Sciences group. His work has spanned radiation detection; core design in light water reactors; advanced reactor physics; depletion, activation, and decay calculations; analysis of large datasets; and risk modeling and analysis. He has also been an author on multiple journal articles, conference papers, and presentations and was a part of a successful Laboratory Directed Research and Development team that researched the dose consequences and fate and transport of TRi-structural ISOtropic particle fuel particles. 

Pavlo has experience with numerous software programs and many coding platforms, such as SCALE, MATLAB, CMS, etc. Pavlo holds an MS in nuclear engineering and a BS in engineering physics, both from the Colorado School of Mines. 

• Core and reactor analysis
• Radiation transport and detection
• Thermal modeling
• Numerical and scientific analysis

• LaTeX
• Matlab
• Microsoft Excel
• Nuclear energy
• Nuclear engineering
• Nuclear fuel cycle
• Nuclear reactor design
• Nuclear reactors
• Radiation detection
• Radiation portal monitoring
• Schedule risk analysis
• Spent nuclear fuel
• Tritium production

• MS, Nuclear Engineering, Colorado School of Mines
• BS, Engineering Physics, Colorado School of Mines

2021

• Condon C.A., P. Ivanusa, A.L. Bunn, and P.J. Jensen. 2021. "Internal Radiation Dose Evaluation For An Unruptured Post Release Tristructural Isotropic Fuel Particle for Advanced and Micro-reactor Applications." Health Physics 120, no. 3:271-277. PNNL-SA-151679 doi: 10.1097/HP.0000000000001310
• Condon C.A., P. Ivanusa, P.J. Jensen, and A.L. Bunn. 2021. "Fate and Consequence of Post-Irradiation TRISO Particles – 21041." In Waste Management Symposia 2021. PNNL-SA-157799
• Ivanusa P., P.J. Jensen, A.L. Bunn, and C.A. Condon. 2021. "Using Analytical Methods to Predict Post-Irradiation Fission Product Release of Low Temperature Tri-Structural Isotropic (TRISO) Particles for Spent Fuel Management." In Waste Management Symposia 2021. PNNL-SA-157810

2020

• Condon C.A., P. Ivanusa, A.L. Bunn, P.J. Jensen, P. Mirick, J.M. Whiting, and C.B. Varnum-Lowry. 2020. Post-Release Consequences of Unruptured TRISO Fuel. PNNL-30444. Richland, WA: Pacific Northwest National Laboratory.
• Ivanusa P., A.L. Bunn, C.A. Condon, and P.J. Jensen. 2020. "Estimated Diffusion Out of a TRISO Particle Under Ambient Conditions." In ANS Virtual Winter Meeting, November 16-19, 2020. La Grange Park, Illinois: American Nuclear Society. PNNL-SA-154306
• Klymyshyn N.A., K. Kadooka, P. Ivanusa, and C.J. Spitz. 2020. "MECHANICAL SHOCK AND VIBRATION ANALYSIS OF SPENT NUCLEAR FUEL CARRIED BY THE ATLAS RAILCAR." In Proceedings of the ASME 2020 Pressure Vessels & Piping Conference (PVP 2020), August 3, 2020, Virtual, Online, 8, Paper No. v008t08a035. New York, New York: American Society of Mechanical Engineers. PNNL-SA-150565
• Klymyshyn N.A., K. Kadooka, P. Ivanusa, C.J. Spitz, and J.F. Fitzpatrick. 2020. 30 cm Drop Modeling. PNNL-30495. Richland, WA: Pacific Northwest National Laboratory. 30 cm Drop Modeling

2019

• Ivanusa P., N.A. Klymyshyn, K. Kadooka, and C.J. Spitz. 2019. "THE SHOCK AND VIBRATION ENVIRONMENT FOR USED NUCLEAR FUEL TRANSPORTATION MODELING." In International High-Level Radioactive Waste Management 2019 (IHLRWM 2019). PNNL-SA-140414
• Klymyshyn N.A., and P. Ivanusa. 2019. "Modeling and Analysis of a One-Third Scale Used Nuclear Fuel Package 30 cm Drop." In Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2019. PNNL-SA-143866
• Klymyshyn N.A., and P. Ivanusa. 2019. Modeling and Analysis to Support Spent Nuclear Fuel Drop Tests. PNNL-29164. Richland, WA: Pacific Northwest National Laboratory.
• Klymyshyn N.A., P. Ivanusa, K. Kadooka, C.J. Spitz, and P.J. Jensen. 2019. "Modeling and Analysis of Used Nuclear Fuel during Normal Conditions of Rail Transportation." In Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2019. PNNL-SA-143868
• Klymyshyn N.A., P. Ivanusa, K. Kadooka, and C.J. Spitz. 2019. "MODELING SHOCK AND VIBRATION ON USED NUCLEAR FUEL DURING NORMAL CONDITIONS OF TRANSPORTATION." In Proceedings of the ASME 2019 Pressure Vessels & Piping Conference (PVP 2019), July 14-19, 2019, San Antonio, TX, 7, Paper No: PVP2019-93619, V007T07A027. New York, New York: ASME. PNNL-SA-140861. doi: 10.1115/PVP2019-93619
• 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.
• Spitz C.J., N.A. Klymyshyn, P. Ivanusa, and K. Kadooka. 2019. "Analyzing the Impact of Buffer Material on Shock and Vibration in Used Nuclear Fuel Transportation." In IHLRWM 2019. PNNL-SA-140438

2018

• Fritz B.G., C.E. Aalseth, H.O. Back, J.C. Hayes, P.H. Humble, P. Ivanusa, and E.K. Mace. 2018. "Prediction of sub-surface 37Ar concentrations at locations in the Northwestern United States." Journal of Environmental Radioactivity 181. PNNL-SA-124417 doi: 10.1016/j.jenvrad.2017.10.005

2017

• Klymyshyn N.A., P. Ivanusa, K. Kadooka, D. Garcia, and J. Smith. 2017. ENSA/DOE Test Plan Modeling and Analysis Support. PNNL-26912. Richland, WA: Pacific Northwest National Laboratory.