Woodruff School of Mechanical Engineering
NRE 8011/8012 and MP 6011/6012 Seminar
Nuclear & Radiological Engineering and Medical Physics Programs
“SCALE analysis of spent nuclear fuel source terms”
Dr. Germina Ilas
Oak Ridge National Laboratory (ORNL)
Thursday, February 16, 2012 at 11:00:00 AM
Boggs Building, Room 3-47, 3rd Fl.
Dr. Bojan Petrovic
Analysis of source terms in nuclear spent fuel applications is discussed, including decay heat, activity, and criticality safety using burnup credit. The analysis is based on depletion and decay capabilities in the SCALE nuclear analysis code system. The underlying codes, nuclear data, computational methodologies and uncertainties in calculated source terms are addressed, with examples presented for different spent fuel types.
Germina Ilas works as research and development staff in the Reactor Physics Group, Reactor and Nuclear Systems Division, at Oak Ridge National Laboratory. She received an MS in Engineering Physics from the University of Bucharest in Romania and a PhD in Nuclear Engineering from Georgia Institute of Technology in Atlanta, Georgia. Her current research areas include source term characterization for spent fuel applications, code validation and uncertainty assessment, and research reactor analysis and design.