Research Projects

Identifying Needed Fire Input Data to Reduce Modeling Uncertainty

Funding source: NEUP/DOE

Collaborators: Prof. Brian Lattimer (VT), Dr. Jun Wang and Prof. Michael Corradidni (University of Wisconsin-Madison), and Dr. Kelly Senecal (Covergent Science)

The research effort will identify the fire parameters that have the largest impact on fire conditions, quantify those parameters contributing to uncertainties in the fire data through Monte Carlo simulation results, and use statistical analysis and machine learning models from simulation results to assess existing data and recommend appropriate new fire tests to reduce uncertainties that are important to risk. Based on this research, we will develop a framework capable of determining the significant contributors to uncertainty in other physical events that are relevant to the risk assessment.

Ignis Database (fire experimental database under construction)

PHILUS Facility 

high-Pressure HIgh Temperature annuLUS flow Facility

Supported by U.S. NRC and Virginia Tech

We are currently building a high-pressure (up to 18 MPa) facility to investigate the post-critical heat flux heat transfer and void fraction. The facility consists of annular channel test section, a Zircaloy fuel rod simulator instrumented with fiber optic temperature sensors, a pressure control system, a heat exchanger, a high-pressure pump, and up to 100 kW power.


Fiber-Optic Distributed Temperature Sensor Application to Quenching Experiments


Mundus. From Latin. World (noun). Clean (advective) 

Investigation of Spent Nuclear Fuel (SNF) Dry Cask System for Long-Term Storage

Funding source: VT IIHCC DA

Collaborators: Prof. Rebecca Cai (MSE) and Prof. Snoja Schmid (STS)

The development of a human-centered society must include a reliable source of energy capable of delivering clean energy in a sustainable and safe manner. Nuclear power is considered a zero-emission energy source that is crucial to meet the global demand to reduce greenhouse gas emissions. To contribute to the nuclear energy development in the area of waste management, we are investigating the chloride-induced stress corrosion cracking (CISCC) under conditions consistently encountered in storage sites using accelerated laboratory experiments to simulate marine environments. Our future goals are combining experimental data and stochastic modeling methods to help us make smart technological and equitable policy decisions in the near future.