Professor
BS Physics, Istanbul University, Istanbul, Turkey
MS Nuclear Engineering, University of Illinois
PhD Nuclear Engineering, University of Illinois
Room E427
201 W. 19th Ave.
Columbus, OH 432010
614-292-4627
Email: aldemir.1
Thrust Area(s): Energy, Fluid, and Thermal SystemsT. Aldemir, G.Torri, M. Marseguerra, E. Zio, J. A. Borkowski, “Using Point Reactor Models and Genetic Algorithms for On-line Global Xenon Estimation in Nuclear Reactors”, Nucl.Technol , 143, 247-255 (September 2003)
I. Munteanu, T. Aldemir, “A Methodology for Probabilistic Accident Management”, Nucl. Technol, 144, 49-62. (October 2003)
P. Wang, T. Aldemir, “Some Improvements in State/Parameter Estimation Using the Cell-to-Cell-Mapping Technique”, Nucl.Sci.Eng., 147, 1-25 (May 2004)
T. Aldemir, “Some Measure Theoretic Issues in Probabilistic Dynamics”, Nucl.Sci.Eng., 155, 497-507 (2007)
T. Aldemir, D. W. Miller, M. Stovsky, J. Kirschenbaum, P. Bucci, L. A. Mangan, A. Fentiman, S. A. Arndt, “Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems”, Nucl.Technol., 159, 167- 191 (2007)
T. Aldemir, M.P. Stovsky, J. Kirschenbaum, D. Mandelli, P. Bucci, L.A. Mangan, D.W. Miller, X. Sun, E. Ekici, S. Guarro, M. Yau, B. Johnson, C. Elks, and, S. A. Arndt, “Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments”, NUREG/CR-6942, U. S. Nuclear Regulatory Commission, Washington, D.C. (August 2007)
T.Aldemir, D.W. Miller, M. P. Stovsky, J. Kirschenbaum, P. Bucci, A. W. Fentiman, L. A. Mangan, Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments, NUREG/CR-6901, U. S. Nuclear Regulatory Commission, Washington, D.C. (February 2006)
K. C. Bledsoe, J. A. Favorite, T. Aldemir, “Material Identification in Finite Cylindrical Geometries Using the Schwinger Inverse Method”, Trans. Am. Nucl. Soc., 95, 545 - 547 (June 2007)
R. Kennedy, K. Metzroth, T. Blue, T. Aldemir, “Preliminary Neutronics Design Study of the Molten Salt Breeder Reactor Concept with MCNP5”, Trans. Am. Nucl. Soc., 95, 649 - 650 (June 2007)