Dave Grabaskas researches and applies qualitative and quantitative risk analysis and safety analysis methods. Techniques include fault tree/event tree (probabilistic risk analysis - PRA, quantitative risk analysis - QRA), success paths, FMEA, HAZOPs, reliability block diagrams, and bow tie analysis.

Research areas include:

• Real time risk management
• Passive safety system reliability
• Mechanistic source term assessment
• Risk-based/risk-informed regulations
• Innovative system/component reliability
• Statistical measures of uncertainty quantification

Committees:

• ASME/ANS Joint Committee on Nuclear Risk Management (JCNRM)
  • Vice Chair: Probabilistic Risk Assessment Standard for Advanced Non-Light Water Nuclear Power Plants

• Generation IV International Forum (GIF) Sodium Fast Reactor
  • U.S. Alternate Representative: Safety and Operation Project Management Board 

Education

PhD – Nuclear Engineering (Ohio State University) 2012
Dissertation: Efficient Approaches to the Treatment of Uncertainty in Satisfying Regulatory Limits

MS – Nuclear Engineering (Ohio State University) 2010
Thesis: Analysis of Transient Overpower Scenarios in Sodium Fast Reactors 

BS – Mechanical Engineering (Ohio State University) 2008