Kurshad Muftuoglu

Short Summary of Experience: Area of expertise includes nuclear reactor safety with emphasis on loss-of-coolant accident, best-estimate methodology development, computational thermal-hydraulics, and system codes development including legacy code maintenance and large-scale software project management. 20+ years of post-baccalaureate experience including ~6 years of graduate research and 14 years of industry experience.

  • PhD Nuclear Engineering, Pennsylvania State University

  • Lafountain, S., Sarikaya, B., Hagaman, J., Sharpe, P., Pappone, D., Muftuoglu, K., Van Doesburg, W., & Nikitin, K. (2015). KKM TRACG LOCA. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 3, (pp. 2375-2388).
  • Li, G., Klebanov, L., Sharpe, P., Muftuoglu, K., & Heck, C. (2015). TRACG application on BWR/2 LOCA. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 3, (pp. 2398-2412).
  • Muftuoglu, K., Pappone, D.C., Holzgrewe, F., & Van Doesburg, W. (2013). Assessment of BWR LOCA analysis for high-burnup fuel fragmentation and dispersal conditions. In Transactions of the American Nuclear Society, 108, (pp. 1104-1106).
  • Kurshad Muftuoglu, A., Li, G., Rambo, J.D., & Sarikaya, B. (2009). Break spectrum studies for tracg realistic BWR LOCA application, invited. In Transactions of the American Nuclear Society, 101, (pp. 848-849).
  • Rambo, J.D., & Muftuoglu, A.K. (2009). Effect of noncondensable gas in BWR core region on LOCA analysis. In Transactions of the American Nuclear Society, 100, (pp. 690-691).
  • Robert, C., Bolger, F., & Muftuoglu, K. (2009). Challenges and opportunities in knowledge management - A case study: Developing expertise in LOCA and containment analyses. In Transactions of the American Nuclear Society, 101, (pp. 1134-1135).
  • Sarikaya, B., Andersen, J.G.M., Bolger, F.T., Fitch, J.R., Heck, C.L., Klebanov, L.A., Muftuoglu, A.K., Shiralkar, B.S., Shum, F.D., & Rock, D.T. (2008). Tracg statistical method for bwr loss-of-coolant accident analyses. In International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 3, (pp. 1443-1446).
  • Muftuoglu, A.K. (2007). Remarks on the use of non-parametric order statistics in realistic LOCA calculations. In Transactions of the American Nuclear Society, 96, (pp. 432-433).
  • Muftuoglu, K., Ohkawa, K., Frepoli, C., & Nissley, M. (2004). Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques. In 12th International Conference on Nuclear Engineering, Volume 3, 3, (pp. 811-818).ASME International. doi: 10.1115/icone12-49499.
  • Yates, B.J., & Gresty, M.A. (2000). Foreword. In Brain Res Bull, 53(1), (p. 1).Elsevier.United States. doi: 10.1016/s0361-9230(00)00301-4.
  • Paul, J.R. (1959). Foreword. In Yale J Biol Med, 32(1), (pp. 1-3).Taylor & Francis.United States. doi: 10.1080/00071686008447833.