Bojan Petrovic
Professor
| Office: | Love Building, Room 020 |
| Phone: | 404.894.8173 |
| Fax: | 404.894.3733 |
| E-mail: | |
Education
- Ph.D., The Pennsylvania State University, 1995
- M.S., The Pennsylvania State University, 1987
- B.S., University of Zagreb, Croatia, 1979
Research Areas and Descriptors
Background
Bojan Petrovic started his career as a Research Staff Member at Rudjer Boskovic Institute (National Research Institute in Croatia) performing research in reactor physics and fuel management. After that, at Penn State University, he expanded his research to transport theory methods development and its applications to nuclear engineering, industry and medicine. Subsequently, during his tenure at Westinghouse Science and Technology, his primary responsibilities were with the development of IRIS (International Reactor Innovative and Secure). He has participated on the IRIS project from its inception, becoming the project Deputy Director. Additionally, he was involved in applied research projects related to novel fuel and advanced nuclear power plants design. His research at Georgia Tech aims to build upon his previous combined theoretical and applied research experience to provide relevant information reflecting real-life needs of nuclear industry.
Research
Dr. Petrovic's current research focuses on advanced reactor design. Specifically, over the past eight years, he has been involved in the development of the International Reactor Innovative and Secure (IRIS), within an international team of 19 organizations from ten countries. IRIS is a medium power (335 MWe) integral-type PWR. It is based on proven light-water technology, but incorporates many innovative solutions that improve its operation, safety, security, and economics. IRIS has been identified by the U.S. Department of Energy within the GNEP program (Global Nuclear Energy Partnership) as an example of a near-term grid-appropriate reactor for worldwide deployment suitable to support the GNEP mission.
Another aspect of Dr. Petrovic's research focuses on methods development in reactor physics and transport theory. Novel reactor designs pose new challenges to analytic tools and thus require improved, more accurate methods. Dr. Petrovic's interest is in developing approaches for using Monte Carlo and hybrid deterministic-Monte Carlo methods in a way that will be practical and relevant for analysis of large, real-life applications.
Dr. Petrovic has strong interest in interdisciplinary areas, and his research projects have included collaboration related to industrial and medical applications of nuclear technology. His research has in the past been sponsored by the Department of Energy, industry, and utilities.
Distinctions
- Westinghouse Corporate-Level Signature Award
- American Nuclear Society
- Reactor Physics Division Program Committee Chair, 2006-Present
- Mathematics and Computation Division Best Benchmark Paper Award, 1995
- Reactor Physics Division, Best Paper Award, 1993
- Nuclear Technology
- Member of the Editorial Board
- Guest Editor for two special issues, 2005
- International Conference on Advances in Nuclear Fuel Management III Technical Program Chair, 2003
- IAEA, Invited Expert at Consultancy and Expert Meetings
Patent
- Nonintrusive Method for the Detection of Concealed Special Nuclear Material, U.S. Patent No. 7,151,815, with F. H. Ruddy, A.R. Dulloo, J.G. Seidel, T.V. Congedo, V. N. Kucukboyaci, December 2006.
Representative Publications
- M. D. Carelli and B. Petrovic. 2006. Here�s Looking at IRIS. Nuclear Engineering International 51(620), 12-18.
- M. D. Carelli,et al. 2004. The Design and Safety Features of the IRIS Reactor. Nuclear Engineering and Design 230, 151-167.
- B. Petrovic and F. Franceschini. 2004. Fuel Management Options in IRIS Reactor for the Extended Cycle. In Proceedings of the 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids. Dubrovnik, Croatia, May 16-20, 2004.
- B. Petrovic and A. Haghighat. 1998. New Directional Theta-Weighted (DTW) Differencing Scheme and Reduction of Estimated Pressure Vessel Fluence Uncertainty. In Reactor Dosimetry (H. Ait Abderrahim, P. D'Hondt and B. Osmera, Eds.), World Scientific Publishing Co., Singapore, 746-753.
- B. Petrovic and A. Haghighat. 1996. Analysis of Inherent Oscillations in Multidimensional SN Solutions of the Neutron Transport Equation. Nucear Science Engineering 124, 31-62.
|
