Georgeta Radulescu, Ph.D.

Affiliations: 
2003 University of Texas at Austin, Austin, Texas, U.S.A. 
Area:
Nuclear Engineering
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"Georgeta Radulescu"

Parents

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Sheldon Landsberger grad student 2003 UT Austin
 (Automated variance reduction for Monte Carlo shielding analyses with MCNP.)
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Publications

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Radulescu G, Banerjee K, Lefebvre RA, et al. (2017) Containment Analysis Capability of UNF-ST&DARDS Nuclear Technology. 199: 299-309
Lefebvre RA, Miller P, Scaglione JM, et al. (2017) Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications Nuclear Technology. 199: 227-244
Radulescu G, Banerjee K, Lefebvre RA, et al. (2017) Shielding Analysis Capability of UNF-ST&DARDS Nuclear Technology. 199: 276-288
Michel-Sendis F, Gauld I, Martinez JS, et al. (2017) SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data Annals of Nuclear Energy. 110: 779-788
Banerjee K, Robb KR, Radulescu G, et al. (2016) Estimation of inherent safety margins in loaded commercial spent nuclear fuel casks Nuclear Technology. 195: 124-142
Radulescu G, Gauld IC, Ilas G, et al. (2014) Approach for validating actinide and fission product compositions for burnup credit criticality safety analyses Nuclear Technology. 188: 154-171
Scaglione JM, Lefebvre RA, Radulescu G, et al. (2013) Integrating data and analysis capabilities for cask-specific safety evaluations 14th International High-Level Radioactive Waste Management Conference, Ihlrwmc 2013: Integrating Storage, Transportation, and Disposal. 1: 425-431
Ilas G, Gauld IC, Radulescu G. (2012) Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE Annals of Nuclear Energy. 46: 43-55
Gauld IC, Radulescu G, Ilas G, et al. (2011) Isotopic depletion and decay methods and analysis capabilities in SCALE Nuclear Technology. 174: 169-195
Radulescu G, Wagner JC. (2011) Review of results for the OECD/NEA phase VII benchmark: Study of spent fuel compositions for long-term disposal 13th International High-Level Radioactive Waste Management Conference 2011, Ihlrwmc 2011. 1: 354-361
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