Georgeta Radulescu

Georgeta Radulescu

Senior R&D Staff

Bio

Dr. Georgeta Radulescu is a Senior Research and Development (R&D) Staff member in the Radiation Transport group, Reactor and Nuclear Systems Division, at Oak Ridge National Laboratory (ORNL), where she has been employed since 2005. Her technical expertise includes application of variance reduction methods to complex shielding calculations, depletion calculations and source term generation, depletion and criticality code validations for spent nuclear fuel (SNF) burnup credit applications, cross-section sensitivity and uncertainty analyses, and nuclear heating determination. At ORNL, Georgeta primarily performed and documented analyses for R&D projects of the U.S. Nuclear Regulatory Commission (NRC) and DOE Office of Energy related to storage and transportation of commercial SNF. Georgeta’s prior work experience includes working as a senior nuclear engineer at the Yucca Mountain Project between 1998 and 2005, where she authored more than twenty engineering calculation reports documenting shielding design and dose rate evaluations for the waste packages and facilities of the proposed geologic repository, and working as a research scientist at the 14-MW TRIGA Research Reactor in Pitesti, Romania, between 1986 and 1995, on research projects for determining absorbed dose in reactor and industrial gamma facilities. Georgeta has an M.S. degree (1986) in Engineering Physics from University of Bucharest, Romania, and M.S. (1997) and Ph.D. (2003) degrees from The University of Texas at Austin.    

Awards

2013: ORNL Significant Event Reward for “Development of Technical Basis for NRC Regulatory Guidance to Enable Expanded Utilization of High-Capacity Spent Nuclear Fuel Storage and Transportation Systems;” Team: J. M. Scaglione, G. Radulescu, I. C. Gauld, D. E. Mueller, G. Illas, W. J. Marshall, and J. C. Wagner.

Projects

Used Nuclear Fuel – Storage, Transportation & Disposal Analysis Resource and Data Systems (UNF-ST&DARDS): Developing model templates to facilitate UNF-ST&DARDS shielding and containment analyses of as-loaded SNF transportation packages.

PWR Burnup Credit: Led the effort to develop the technical basis and recommendations in the NRC Interim Staff Guidance ISG-8 Rev. 3 concerning the depletion uncertainty from burnup credit criticality safety calculations using actinides and fission products.

Publications

R. A. Lefebvre, P. Miller, J. M. Scaglione, K. Banerjee, J. L. Peterson, G. Radulescu. K. R. Robb, A. B. Thompson. H. Lijenfeldt, J. P. Lefebvre, "Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications," Nucl. Technol., 199(3), 227-244 (2017). dx.doi.org/10.1080/00295450.2017.1314747

G. Radulescu, K. Banerjee, R. A. Lefebvre, L. P. Miller, and J. M. Scaglione, "Shielding Analysis Capability of UNF-ST&DARDS," Nucl. Technol., 199(3), 276-288 (2017). dx.doi.org/10.1080/00295450.2017.1307643

G. Radulescu, K. Banerjee, R. A. Lefebvre, L. P. Miller, and J. M. Scaglione, "Containment Analysis Capability of UNF-ST&DARDS," Nucl. Technol., 199(3), 299-309 (2017). dx.doi.org/10.1080/00295450.2017.1348800

F. Michel-Sandis et. al., An OECD NEA database of spent nuclear fuel isotopic assay, reactor design specifications, and operating data, Annals of Nuclear Energy 110 (2017) 779-788. http://dx.doi.org/10.1016/j.anucene.2017.07.022 

K. Banerjee, H. Liljenfeldt, P. L. Miller, J. L. Peterson, R. A. Joseph III, J. B. Clarity, G. Radulescu, R. A. Lefebvre, and J. M. Scaglione “Consolidating Data on Spent Nuclear Fuel into a Unified Database,” Trans. Am. Nucl. Soc. 115(1), 279-282 (2016).

K. Banerjee, K. R. Robb, G. Radulescu, P. L. Miller, J. M. Scaglione, J. M. Cuta, and H. Liljenfeldt, “UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems,” PATRAM 2016, Japan Society of Mechanical Engineers and Atomic Energy Society of Japan, Kobe, Japan, Sept. 18-23, 2016.

K. Banerjee, K. R. Robb, G. Radulescu, J. M. Scaglione, J. C. Wagner, J. B. Clarity, R. A. LeFebvre, J. L. Peterson, "Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks," Nucl. Technol., 195(2), 124-142 (2016). dx.doi.org/10.13182/NT15-112

G. Radulescu and K. J. Connolly, “A Parametric Analysis of Factors Affecting Calculations of Estimated Dose Rates from Spent Nuclear Fuel Shipments,” Proc. of the WM2016 Conference, Phoenix, Arizona, March 6-10, 2016.

G. Radulescu, R. A. Lefebvre, K. Banerjee, P. Miller, and J. M. Scaglione, “Shielding Analysis Capability of UNF-ST&DARDS,” Trans. Am. Nucl. Soc., 113 (2015).

G. Radulescu, R. A. Lefebvre, P. Miller, A. B. Thompson, K. Banerjee, and J. M. Scaglione, “Containment Analysis Capability of UNF-ST&DARDS,” Trans. Am. Nucl. Soc., 113 (2015).

K. J. Connolly and G. Radulescu, “Long Range Dose Rate Models for Spent Nuclear Fuel Transportation Casks,” Trans. Am. Nucl. Soc., 113 (2015).

W. J. Marshall, B. J. Ade, S. M. Bowman, I. C. Gauld, G. Ilas, U. Mertyurek, and G.  Radulescu, “Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems,” Proc. of the ICNC 2015, Charlotte, North Carolina, Sept. 13-17, 2015.

J. M. Scaglione, R. L. Lefebvre, K. Banerjee, G. Radulescu, and K.R. Robb, “A Unified Spent Nuclear Fuel Database and Analysis System,” Proc. of the IAEA International Conference on Management of Spent Fuel from Nuclear Power Reactors – An Integrated Approach to the Back-End of the Fuel Cycle, Vienna, Austria, June 15-19, 2015.

J. M. Scaglione, G. Radulescu, W. J. Marshall, and K. R. Robb, A Quantitative Impact Assessment of Hypothetical Spent Fuel Reconfiguration in Spent Fuel Storage Casks and Transportation Packages, NUREG/CR-7203 (ORNL/TM-2013/92), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, Oak Ridge, TN (2015).

W. J. Marshall, B. J. Ade, S.M. Bowman, I. C. Gauld, G. Ilas, U. Mertyurek, and G. Radulescu, Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, NUREG/CR-7194 (ORNL/TM-2014/240), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2015).

K. Banerjee, J. M. Scaglione, R. L. Lefebvre, G. Radulescu, and K. R. Robb, “Streamlining Analysis Capabilities for SNF Management,” Proc. of the WM2015 Conference, Phoenix, AZ, March 15-19, 2015.

J. M. Scaglione, G. Radulescu, K. R. Robb, and W. J. Marshall, “Consequence Assessment of Fuel Reconfiguration for Dry Storage and Transportation Packages,” Trans. Am. Nucl. Soc., 111, 330-333 (2014).

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, “Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses,” Nucl. Technol., 188(2), 154–171 (2014). dx.doi.org/10.13182/NT13-154 

G. Radulescu, D. E. Peplow, M. L. Williams, and J. M. Scaglione, “Dose Rate Analysis of As-Loaded Spent Nuclear Fuel Casks,” Proc. of the 18th Topical Meeting of the Radiation Protection & Shielding Division of ANS, Knoxville, TN, Sept. 14 – 18, 2014.

D. E. Peplow, G. Radulescu, M. L. Williams, and R. L. Lefebvre,, ”SCALE Enhancements for Detailed Cask Dose Rate Analysis,” Proc. of the 18th Topical Meeting of the Radiation Protection & Shielding Division of ANS, Knoxville, TN, Sept. 14 – 18, 2014.

G. Radulescu, R. L. Lefebvre, D. E. Peplow, M. L. Williams, and J. M. Scaglione, “Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents,” Proc. of the 55th Institute of Nuclear Materials Management (INMM) Annual Meeting, Atlanta, GA, July 20-24, 2014.

J. M. Scaglione, G. Radulescu, K. R. Robb, W. J. Marshall, J. C. Wagner, M. Flanagan, M. Aissa, and Z. Li, “Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios," Proc. of PATRAM 2013, San Francisco, CA, August 18-23, 2013.

J. M. Scaglione, R. L. Lefebvre, G. Radulescu, H. J. Smith, D. Ilas, K. R. Robb, J. C. Wagner, H. E. Adkins, T. E. Michener, and D. Vinson, “Integrating Data and Analysis Capabilities for Cask-Specific Safety Evaluations,” Proc. of the 14th International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 28 – May 2, 2013.

J. M. Scaglione, A. Caswell, J. B. Clarity, and G. Radulescu, “Considerations for an Integrated Storage, Transportation, and Disposal Canister,” Proc. of the 14th International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 28 – May 2, 2013.

A. M. Bevill, G. Radulescu, J. M. Scaglione, and R. L. Howard, “ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository,” Proc. of the 14th International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 28 – May 2, 2013.

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses―Isotopic Composition Predictions, NUREG/CR-7108 (ORNL/TM-2011/509), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2012).

G. Radulescu and J. C. Wagner,  Burn-up Credit Criticality Safety Benchmark Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal, A Report by the Expert Group on Burn-up Credit Criticality NEA Nuclear Science Committee, Working Party on Nuclear Criticality Safety, ISBN 978-92-64-99172-9, NEA No. 6998, Nuclear Energy Agency, Organisation for Economic Co-operation and Development, February 2012.

G. Ilas, I. C. Gauld, and G. Radulescu, “Validation of new depletion capabilities and ENDF/B–VII data libraries in SCALE,” Annals of Nuclear Energy, 46, 43–55 (2012). 

I. C. Gauld, G. Ilas, and G. Radulescu, Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel, NUREG/CR-7012 (ORNL/TM-2010/41), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2011).

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, “An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions,” Proc. of the 9th International Conference on Nuclear Criticality Safety (ICNC 2011), Edinburgh, United Kingdom, Sept. 19–22, 2011.

I. C. Gauld, G. Radulescu, G. Ilas, B. D. Murphy, M. L. Williams, and D. Wiarda, “Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE,” Nucl. Technol., 174, 169–195 (2011). dx.doi.org/10.13182/NT11-3

G. Radulescu and J. C. Wagner, “Review of Results for the OECD/NEA Phase VII Benchmark: Study of Spent Fuel Compositions for Long-Term Disposal,” Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, NM, April 10–14, 2011.

G. Radulescu, Propagation of Isotopic Bias and Uncertainty to Criticality Safety Analyses of PWR Waste Packages, ORNL/TM-2010/116, Oak Ridge National Laboratory (2010).

G. Radulescu and E. D. Blakeman, “Iodine-125 Brachytherapy Seed Benchmark,” Proc. American Nuclear Society Radiation Protection and Shielding Division 2010 Topical Meeting, Las Vegas, NV, April 18–23, 2010.

G. Radulescu, I. C. Gauld, and G. Ilas, SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions, ORNL/TM-2010/44, Oak Ridge National Laboratory (2010).

G. Radulescu, I. C. Gauld, and G. Ilas “Evaluation of PWR Isotopic Composition Data,” Trans. Am. Nucl. Soc., 101, 688 (2009).

I. C. Gauld, G. Radulescu, and G. Ilas, “SCALE Validation Experience Using an Expanded Isotopic Assay Database for Spent Nuclear Fuel,” Proc. of the IAEA/CSN International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, Oct. 27–30, 2009.

G. Radulescu and I. C. Gauld, “Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE“, Proc. of the 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, Richland, WA, Sept. 13–17, 2009.

G. Radulescu, D. E. Mueller, and J. C. Wagner, “Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit,” Nucl. Technol., 167(2), 268–287 (2009). dx.doi.org/10.13182/NT09-A8963

G. Radulescu, D. E. Mueller, and J. C. Wagner, Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit, NUREG/CR-6951 (ORNL/TM-2006/87), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2007).

G. Radulescu, D. E. Mueller, S. Goluoglu, D. F. Hollenbach, and P. B. Fox, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, ORNL/TM-2007/127, Oak Ridge National Laboratory (2007).

G. Radulescu, D. E. Mueller, and J. C. Wagner, “Evaluation of Applicability of CRC Models for Burnup Credit Validation,”  Trans. Am. Nucl. Soc. 97, 151-153 (2007).

G. Radulescu and S. Su, “Dose Rate Evaluation for Spent Fuel Aging Areas at Yucca Mountain,” Trans. Am. Nucl. Soc., 92, 29 (2005).

G. Radulescu and J. S. Tang, “Shielding Evaluations of Waste Package Designs,” Proc. of the 12th Biennial RPSD Topical Meeting, Santa Fe, NM, April 14–18, 2002.

J. S. Tang and G. Radulescu, “Radiolytic Production of Nitric Acid Outside a 21-PWR Waste Package,” Proc. of the 12th Biennial RPSD Topical Meeting, Santa Fe, NM, April 14–18, 2002.

G. Radulescu, Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Evaluation of the Relative Power Experiments for the Saxton Partial Plutonium Core, ORNL/SUB/99-XSZ175V-4, Oak Ridge National Laboratory (2001).

N. M. Abdurrahman, I. Carron, and G. Radulescu, Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Saxton Critical Experiments, ORNL/SUB/00-XSZ175V-2, Oak Ridge National Laboratory (2000).

G. Radulescu, J. S. Tang, and T. W. Doering, “Evaluation of the Effect of Source Geometry Models on Dose Rates of Waste Packages.” J. Nucl. Sci. Tech., Supplement 1, 320–323 (2000) (9th International Conference on Radiation Shielding, Tsukuba, Japan, 17–22 Oct. 1999).

N. M. Abdurrahman, G. Radulescu, and I. Carron, “Benchmark Calculations for Critical Experiments of the Saxton Plutonium Program,” Nucl. Technol., 127, 315–331 (1999).

G. Radulescu and N. M. Abdurrahman, “Benchmark Calculations for Relative Power Experiments of the Saxton Plutonium Critical Experiments,” Trans. Am. Nucl. Soc., 78, 250 (1998).

N. M. Abdurrahman, M. Yavuz, and G. Radulescu, “MCNP Analysis of PNL Split-Table Critical Experiments Containing Mixed-Oxide Fuels,” Trans. Am. Nucl. Soc., 77, 213 (1997).

G. Radulescu and N. M. Abdurrahman, “MCNP Criticality Calculations of the Saxton Plutonium Program Experiments,” Trans. Am. Nucl. Soc., 76, 231 (1997).

G. Radulescu, I. Pop, and C. Toma, “Measurement of Absorbed Dose in the 14-MW TRIGA Reactor,” Proc. of the Twelfth European TRIGA Users Conference, Pitesti, Romania, Sept. 28 – Oct. 1, 1992.