selected publications academic article Mendoza, M., & Tsvetkov, P. V. (2024). An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Unknown fault detection. 171, 105167-105167. Gatchalian, R., & Tsvetkov, P. V. (2024). Traditional machine learning methods in predicting the physics of subcritical systems in source-equilibrium. Annals of Nuclear Energy. 201, 110413-110413. Mendoza, M., & Tsvetkov, P. V. (2024). An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Fault diagnosis. 168, 104989-104989. Gates, J. T., & Tsvetkov, P. V. (2024). Testing of fiber optic based sensors for advanced reactors in the Texas A&M University TRIGA reactor. 196, 110222-110222. Gatchalian, R., & Tsvetkov, P. V. (2024). Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks. ahead-of-print(ahead-of-print), 1-24. Clarno, K. T., Barlow, J. E., Sawyer, T., Scherr, J., Hearne, J., & Tsvetkov, P. (2023). Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark. Annals of Nuclear Energy. 194, 110092-110092. Scherr, J., & Tsvetkov, P. (2023). Scoping Studies of Reactor Core Parameters in Support of the Abilene Christian University Molten Salt Research Reactor. 209(11), 1733-1746. Weiss, A. G., Aranguren, B., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M. (2023). A Data-driven approach to predicting neutron penetration through media. Annals of Nuclear Energy. 192, 109953-109953. Weiss, A. G., V. Tsvetkov, P., Hearne, J., Kimber, M. L., Wootan, D. W., & McDeavitt, S. M. (2023). A sensitivity analysis to predict the neutronics behavior of samples irradiated in the VTR rabbit system. Annals of Nuclear Energy. 185, 109708-109708. Gatchalian, R., & Tsvetkov, P. V. (2023). Reactor physics analysis of a Source-driven TRIGA configuration in subcritical domain. Annals of Nuclear Energy. 186, 109787-109787. McDeavitt, S. M., Wootan, D., Kimber, M., Kirkland, K. V., Ortega, L. H., Perez-Nunez, D., ... Woolstenhulme, N. E. (2023). Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies. 197(11), 2840-2852. Mendoza, M., & V. Tsvetkov, P. (2022). An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Power transient identification. PROGRESS IN NUCLEAR ENERGY. 156. Stolte, K. N., & V. Tsvetkov, P. (2022). x-MeRA: Computationally efficient adaptive mesh refinement of Monte Carlo mesh based tallies. Annals of Nuclear Energy. 182. Patel, V., Navarro, J., Windes, W., & Tsvetkov, P. (2022). An uncertainty quantification method relevant to material test reactors. Annals of Nuclear Energy. 165, 108629-108629. Passons, B., & Tsvetkov, P. (2022). Design and performance analysis of a mobile, land-based micro-reactor. Annals of Nuclear Energy. 165, 108688-108688. Mueller, C., & Tsvetkov, P. (2021). A network approach to full core temperature analysis in advanced nuclear heat-pipe systems. Annals of Nuclear Energy. 160, 108354-108354. Weiss, A. G., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M. (2021). A novel method for the design and selection of neutron-attenuating media. Annals of Nuclear Energy. 160, 108368-108368. Mueller, C., & Tsvetkov, P. (2021). A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis. Annals of Nuclear Energy. 160, 108393-108393. Mendoza, M., Tsvetkov, P. V., & Lewis, M. (2021). Multi-modal global surveillance methodology for predictive and on-demand characterization of localized processes using cube satellite platforms and deep learning techniques. 22, 100518-100518. Ganapol, B., & Tsvetkov, P. (2021). CHAPTER 5 DIFFUSION THEORY. EPJ Web of Conferences. 247, 14005-14005. Stratton, C., & Tsvetkov, P. (2020). Experimental analysis of fiber optic responses in ionizing radiation environments for distributed sensing applications. 130, 103519-103519. Hearne, J. A., & Tsvetkov, P. V. (2020). Physical anomaly detection and identification using Cerenkov radiation. Annals of Nuclear Energy. 142, 107424-107424. Hearne, J. A., & Tsvetkov, P. V. (2020). Three dimensional reactor power profile reconstruction using Cerenkov radiation. Annals of Nuclear Energy. 142, 107426-107426. Hearne, J. A., & Tsvetkov, P. V. (2020). Power Profile Reconstruction and Anomaly Detection Approach for FHRs Using Cerenkov Radiation. Nuclear Technology. 206(11), 1740-1750. Mueller, C., & Tsvetkov, P. (2020). Novel design integration for advanced nuclear heat-pipe systems. Annals of Nuclear Energy. 141, 107324-107324. Hearne, J. A., & Tsvetkov, P. V. (2020). Response function generation for Cerenkov radiation production and transport in a TRIGA coolant channel. Annals of Nuclear Energy. 138, 107200-107200. Hearne, J. A., & Tsvetkov, P. V. (2020). Spatial power profiling method using visual information in reactors with optically transparent coolants. Annals of Nuclear Energy. 137, 107071-107071. Hearne, J. A., & Tsvetkov, P. V. (2019). Analysis of the transmutation of long lived fission products using a charged particle beam. Annals of Nuclear Energy. 133, 501-510. Spencer, K. Y., Tsvetkov, P. V., & Janell, J. J. (2019). Validation of the GAMMA-PC methodology for dry cask loading optimization. PROGRESS IN NUCLEAR ENERGY. 117, 103038-103038. Luan, X., & Tsvetkov, P. V. (2019). Novel consistent approach in controllability evaluations of point reactor kinetics models. Annals of Nuclear Energy. 131, 496-506. Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J. (2019). A greedy memetic algorithm for a multiobjective dynamic bin packing problem for storing cooling objects. Journal of Heuristics. 25(1), 1-45. Scherr, J., & Tsvetkov, P. (2018). Design strategies for LWR and VHTR test environments in a fast spectrum reactor. Annals of Nuclear Energy. 120, 219-235. Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J. (2018). Optimization of dry cask loadings for used nuclear fuel management strategies. PROGRESS IN NUCLEAR ENERGY. 108, 11-25. Scherr, J., & Tsvetkov, P. (2018). Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor. Annals of Nuclear Energy. 113, 15-24. Kumar, A., & Tsvetkov, P. V. (2015). A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis. Annals of Nuclear Energy. 85, 27-35. Kumar, A., Tsvetkov, P. V., & McClarren, R. G. (2015). Linear regression and sensitivity analysis in nuclear reactor design. Annals of Nuclear Energy. 85, 798-811. Kumar, A., & Tsvetkov, P. V. (2015). Optimization of U-Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms. Annals of Nuclear Energy. 85, 885-892. Rashdan, A. A., & Tsvetkov, P. (2015). Parametric evaluation of an SMR design domain. Annals of Nuclear Energy. 85, 958-978. Yancey, K., & Tsvetkov, P. V. (2015). Variability in spent fuel inventory data. PROGRESS IN NUCLEAR ENERGY. 81, 184-195. Connolly, K. J., Rahnema, F., & Tsvetkov, P. V. (2015). Prismatic VHTR neutronic benchmark problems. 285, 207-240. Kelly, R., Tsvetkov, P., Chirayath, S., Poston, J., & Kitcher, E. (2015). UNCERTAINTY QUANTIFICATION OF CONCRETE UTILIZED IN DRY CASK STORAGE. Nuclear Technology. 190(1), 72-87. Yancey, K., & Tsvetkov, P. V. (2014). Quantification of US spent fuel inventories in nuclear waste management. Annals of Nuclear Energy. 72, 277-285. Kumar, A., Chirayath, S. S., & Tsvetkov, P. V. (2014). Analysis of a sustainable gas cooled fast breeder reactor concept. Annals of Nuclear Energy. 69, 252-259. Patel, V., & Tsvetkov, P. (2013). Multi-module approach to modularity in a neutronically coupled high temperature multi-modular system. Nuclear Engineering and Design. 263, 411-418. Cuvelier, M., & Tsvetkov, P. V. (2013). TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs. 55, 137-150. Patel, V., & Tsvetkov, P. (2013). Concept of a high temperature integrated multi-modular thermal reactor. Annals of Nuclear Energy. 55, 312-321. Rashdan, A. A., & Tsvetkov, P. (2012). Hierarchical Integrated Parameters Exploration in Systems Modeling. 99(1), 1-13. Ames, D., & Tsvetkov, P. V. (2011). High-fidelity system modeling of advanced nuclear energy systems approaching a zero-nuclear-waste limit. PROGRESS IN NUCLEAR ENERGY. 53(6), 626-632. Alajo, A. B., & Tsvetkov, P. V. (2011). Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTRs. Annals of Nuclear Energy. 38(1), 88-97. Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D. (2010). "Used fuel" vectors and waste minimization strategies for VHTRS operating without refueling. Nuclear Engineering and Design. 240(10), 2458-2465. Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D. (2010). VHTR-based systems for autonomous co-generation applications. Nuclear Engineering and Design. 240(10), 2451-2457. Lewis, T., & Tsvetkov, P. V. (2009). Physics Features of TRU-Fueled VHTRs. 2009, 1-7. Tsvetkov, P. V., Alajo, A. B., & Ames, D. (2009). Autonomous Control Strategies for Very High Temperature Reactor Based Systems for Hydrogen Production. 131(5), 052906. Tsvetkov, P. V., Lewis, T., & Alajo, A. B. (2009). TRU-Fueled Very High Temperature Reactors for Applications Requiring an Extended Operation With Minimized Control and No Refueling. 131(5), 052907. Tsvetkov, P. V., Ames, D., Alajo, A. B., & Lewis, T. (2008). Spectrum shifting as a mechanism to improve performance of VHTRs with advanced actinide fuels. Nuclear Engineering and Design. 238(8), 1958-1964. Valko, J., Tsvetkov, P. V., & Hoogenboom, J. E. (2000). Calculation of the Dancoff factor for pebble bed reactors. 135(3), 304-307. book Pioro, I. (2016). Handbook of Generation IV Nuclear Reactors. Woodhead Publishing. Tsvetkov, P. (2011). Nuclear Power Control, Reliability and Human Factors. Ed. Nuclear Power Control, Reliability and Human Factors. IntechOpen. Tsvetkov, P. (2011). Nuclear Power Deployment, Operation and Sustainability. Ed. Nuclear Power Deployment, Operation and Sustainability. IntechOpen. Tsvetkov, P. (2011). Nuclear Power Operation, Safety and Environment. Ed. Nuclear Power Operation, Safety and Environment. IntechOpen. Tsvetkov, P. (2011). Nuclear Power System Simulations and Operation. Ed. Nuclear Power System Simulations and Operation. IntechOpen. Krivit, S. B., & Lehr, J. H. (2011). Nuclear Energy Encyclopedia Science, Technology, and Applications. JOhn Wiley & Sons. chapter Abuqudaira, T., Tsvetkov, P., & Sabharwall, P. (2023). Perspective Chapter: Assessment of Nuclear Sensors and Instrumentation Maturity in Advanced Nuclear Reactors. Dr. Pavel V. Tsvetkov. (Eds.), Nuclear Fission - From Fundamentals to Applications. (pp. Ch.-4). IntechOpen. Tsvetkov, P. (2023). Chapter 4 Gas-cooled Fast Reactors (GFRs). Handbook of Generation IV Nuclear Reactors. (pp. 167-172). Elsevier. Tsvetkov, P. (2023). Chapter 9 Generation IV: United States. Handbook of Generation IV Nuclear Reactors. (pp. 287-301). Elsevier. Tsvetkov, P. V. (2021). Management of the Nuclear Waste Via Disposition or Transmutation. Encyclopedia of Nuclear Energy. (pp. 465-477). Elsevier. Tsvetkov, P. V., & Stachowski, R. E. (2021). Physics of the Fission Chain Reaction in Thermal and Fast Reactors. Encyclopedia of Nuclear Energy. (pp. 172-186). Elsevier. Tsvetkov, P. (2016). Gas-cooled fast reactors. Handbook of Generation IV Nuclear Reactors. (pp. 91-96). Tsvetkov, P. (2016). Generation IV: USA. Handbook of Generation IV Nuclear Reactors. (pp. 223-239). Tsvetkov, P., Waltar, A., & Salvatores, M. (2012). Fuel Management. Fast Spectrum Reactors. (pp. 135-185). Springer Nature. Tsvetkov, P., Waltar, A., & Todd, D. (2012). Introductory Design Considerations. Fast Spectrum Reactors. (pp. 23-38). Springer Nature. Tsvetkov, P., Waltar, A., & Todd, D. (2012). Kinetics, Reactivity Effects, and Control Requirements. Fast Spectrum Reactors. (pp. 111-133). Springer Nature. Tsvetkov, P., & Waltar, A. (2012). Nuclear Data and Cross Section Processing. Fast Spectrum Reactors. (pp. 77-109). Springer Nature. Tsvetkov, P., Waltar, A., & Todd, D. (2012). Nuclear Design. Fast Spectrum Reactors. (pp. 49-76). Springer Nature. Tsvetkov, P., Waltar, A., & Todd, D. (2012). Reactor Plant Systems. Fast Spectrum Reactors. (pp. 365-407). Springer Nature. Tsvetkov, P., Waltar, A., & Todd, D. (2012). Sustainable Development of Nuclear Energy and the Role of Fast Spectrum Reactors. Fast Spectrum Reactors. (pp. 3-22). Springer Nature. Waltar, A., Todd, D., & Tsvetkov, P. (2011). Fast Reactor Simulations. Fast Spectrum Reactors. Springer. Tsvetkov, P. V. (2011). Basic Concepts of Nuclear Fission. Nuclear Energy Encyclopedia. (pp. 45-49). Wiley. Tsvetkov, P. V. (2011). Direct Energy Conversion Concepts. Nuclear Energy Encyclopedia. (pp. 569-579). Wiley. Tsvetkov, P. V., & Ames, D. E. (2011). Electrical Generation from Nuclear Power Plants. Nuclear Energy Encyclopedia. (pp. 57-64). Wiley. Tsvetkov, P. V. (2011). Fission Energy Usage: Status, Trends and Applications. Nuclear Energy Encyclopedia. (pp. 159-163). Wiley. Tsvetkov, P. V. (2011). GraphiteModerated Fission Reactor Technology. Nuclear Energy Encyclopedia. (pp. 187-192). Wiley. Tsvetkov, P., & Guy, T. (2010). Advanced Magnetic-Nuclear Power Systems for Reliability Demanding Applications Including Deep Space Missions. Nuclear Power. IntechOpen. conference paper Passmore, J., Dean, D., & Tsvetkov, P. (2023). Exploratory Analysis of Parametric Dependencies in Molten Salt Reactor Design Domains. Transactions of the American Nuclear Society. 843-844. Abuqudaira, T., Tsvetkov, P., & Sabharwall, P. (2023). Fuel Flow Modeling Under Thermal Fluidics Considerations Within Operational Domains of Molten Salt Reactors. 3208-3221. Abuqudaira, T., Tsvetkov, P., & Sabharwall, P. (2023). Neutronics/Thermal-Hydraulics Coupling in Simulation of Advanced Nuclear Reactors Watson, D., Gatchalian, R. D., Hsieh, H., Bhat, P., & Tsvetkov, P. (2023). SpaceX Falcon Heavy Mass Constraints as Design Driver for Practical Heat Pipe Stirling Micro Reactors. 305-311. Abuqudaira, T., Tsvetkov, P., & Sabharwall, P. (2023). The Effect of Point Reactor Kinetics Solvers on the Accuracy of Nuclear Reactor Simulations. Transactions of the American Nuclear Society. 451-454. Gatchalian, R., & Tsvetkov, P. (2022). Machine Learning Approach in Determining Reactor Physics of Subcritical Reactors Tsvetkov, P., Erickson, A., Sabharwall, P., & Mendoza, M. (2022). Maintaining End-to-End Safeguards Continuity-of-Knowledge on Mobile, Autonomous and remotely Operated Microreactors Stolte, K., & Tsvetkov, P. (2022). Historical review and proof-of-concept future method demonstration of adaptive mesh refinement in nuclear engineering for increased fidelity and computational efficiency Biegalski, S., Tsvetkov, P., Tao, Y., Sobes, V., Pazdernik, K., Labov, S., ... Hero, A. (2021). 2020 ETI Annual Summer School: Data Science and Engineering McDeavitt, S., Kimber, M., Kirkland, K., Ortega, L., Perez-Nunez, D., Tsvetkov, P., ... Weiss, A. (2020). Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor. 1408-1411. Hearne, J., McDeavitt, S., Scherr, J., Tsvetkov, P., & Wootan, D. (2019). Analysis of the VTR In-Core Environment with the Rabbit Delivery System Enabling Encapsulated Irradiations. 1427-1430. Smith, K., Tsvetkov, P., Kim, M. H., Shao, L., & Chirayath, S. (2019). Floating Micro-Modular Reactor Concept for Localized Outages. Transactions of the American Nuclear Society. 680-682. Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J. (2018). Development of a greedy method for used fuel selection in dry cask storage. AISTech - Iron and Steel Technology Conference Proceedings. 151-154. Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J. (2018). Development of a greedy method for used fuel selection in dry cask storage. Transactions of the American Nuclear Society. 151-154. Stratton, C., & Tsvetkov, P. (2017). Experiments with distributed measurement of radiation by fiber optic intrinsic sensors. Transactions of the American Nuclear Society. 460-462. Tsvetkov, P., Rosaire, C., Scherr, J., Hearne, J., & Marcantel, G. (2017). In-core feature identification using neutron, gamma, and temperature data. Transactions of the American Nuclear Society. 1088-1090. Tsvetkov, P. (2017). Integral modularity as a design approach for customizable multi-product output applications. Transactions of the American Nuclear Society. 1133-1135. Rahnema, F., Petrovic, B., Singh, P., Sun, X., Tsvetkov, P., Yoder, G., Zhang, D., & Zhang, J. (2017). Integrated approach to Fluoride High Temperature Reactor (FHR) technology development Stratton, C., & Tsvetkov, P. (2017). Point source method of reconstruction from distributed measurement. Transactions of the American Nuclear Society. 443-444. Tsvetkov, P., Cardenas, A., Manic, M., & Wilhelm, J. (2017). Protection via cyber security event analysis framework using full-scope plant simulator capabilities. Transactions of the American Nuclear Society. 1136-1138. Do Carmo, M. G., & Tsvetkov, P. (2016). Aquatic availability needs analysis of nuclear power scenarios for electricity and potable water production. 509-513. Mathis, D. A., & Tsvetkov, P. V. (2016). Design options for ultra-compact nuclear driven power sources for field applications. 570-576. Scherr, J. B., & Tsvetkov, P. V. (2016). Fast spectrum materials test reactor with variable neutron spectra in support of next generation nuclear power plant and light water reactor sustainability R&D. 1614-1630. Kelsey, J., Morell-Pacheco, A., Hughes, T., Whitman, N., & Tsvetkov, P. (2016). VASIMR interfaced high temperature gas-cooled fast reactor for space applications. Transactions of the American Nuclear Society. 80-83. Kumar, A., & Tsvetkov, P. V. (2015). An optimization methodology in nuclear reactor design using genetic algorithms and regression analysis. Transactions of the American Nuclear Society. 165-169. Scherr, J. B., & Tsvetkov, P. V. (2015). Fast spectrum material's testing reactor with variable energy spectra to support advanced reactors program and light water reactor sustainability program R&D. Transactions of the American Nuclear Society. 1115-1118. Stratton, C., & Tsvetkov, P. (2015). High spatial resolution reactor power reconstruction from external core distributed measurement. Transactions of the American Nuclear Society. 222. Kumar, A., & Tsvetkov, P. V. (2015). Parametric analysis and optimization using multivariate regression analysis and genetic algorithms. Transactions of the American Nuclear Society. 148-152. Al Rashdan, A., Tsvetkov, P., & Vierow, K. (2014). Considerations of water injection timing and volume in accident scenarios relevant to the Fukushima-Daiichi nuclear power plant. Transactions of the American Nuclear Society. 953-955. Al Rashdan, A., & Tsvetkov, P. (2014). Evaluation of an integral homogenization approach for LWSMR core neutronics discretization. Transactions of the American Nuclear Society. 1234-1236. Stratton, C., & Tsvetkov, P. (2014). Reactor power reconstruction from external core distributed measurement. Transactions of the American Nuclear Society. 475-476. McIntyre, P., Assadi, S., Badgley, K., Baker, W., Comeaux, J., Gerity, J., ... Tsvetkov, P. (2013). Accelerator-Driven Subcritical Fission In Molten Salt Core: Closing The Nuclear Fuel Cycle For Green Nuclear Energy. AIP Conference Proceedings. 636-642. Sattarov, A., Assadi, S., Badgley, K., Baty, A., Comeaux, J., Gerity, J., ... Mann, T. (2013). Neutronics of accelerator-driven subcritical fission for burning transuranics in used nuclear fuel. AIP Conference Proceedings. 245-250. Johnson, M. P., & Tsvetkov, P. V. (2013). 3D mapping and reconstruction for in-core monitoring in advanced reactors. Transactions of the American Nuclear Society. 1120-1122. McIntyre, P., Tsvetkov, P., Assadi, S., Pogue, N., & Sattarov, A. (2013). Accelerator-based neutron damage testing-high energy neutrons for accelerated material qualification. Transactions of the American Nuclear Society. 22-25. McIntyre, P., Assadi, S., Comeaux, J., Kellams, J., Melconian, K., Pogue, N., ... Tsvetkov, P. (2013). Accelerator-driven subcritical fission in a molten salt core: Destroy the transuranics in UNF. Transactions of the American Nuclear Society. 337-340. Al Rashdan, A., Patel, V., & Tsvetkov, P. (2013). Energy mix grid aggregation analysis. Transactions of the American Nuclear Society. 1123-1125. Johns, J. M., Johnson, M. P., Tsvetkov, P. V., & Bragg-Sitton, S. M. (2013). Fiberoptics-based sensing for real-time 3D in-core monitoring in NGNP/VHTR environments. Transactions of the American Nuclear Society. 1033-1036. McIntyre, P., Assadi, S., Gerity, J., Johns, J., Pogue, N., Sattarov, A., & Tsvetkov, P. (2013). Safety and reliability in accelerator-driven subcritical fission in a molten salt core. Transactions of the American Nuclear Society. 341-344. Johns, J. M., & Tsvetkov, P. V. (2012). Developmoent of TRIGA-based experimental device for fiber optics in-core instrumentation testing for VHTRs. 3515-3524. Johnson, M., Tsvetkov, P., & Lucas, S. (2012). Short-time scale behavior modeling within long-time scale fuel cycle evaluations. 1835-1846. Tsvetkov, P. V., Bragg-Sitton, S. M., Johns, J. M., & Johnson, M. P. (2012). 3D in-core monitoring in advanced reactor environments. Transactions of the American Nuclear Society. 626-627. Cuvelier, M. H., & Tsvetkov, P. V. (2012). 235U prompt neutron fission spectrum data sensitivity/uncertainty effects in fuel cycle performance parameters Tsvetkov, P. V., Manic, M., & Sabharwall, P. (2012). Simulations of dynamics and control of advanced reactor systems using artificial neural networks. Transactions of the American Nuclear Society. 628-629. Tsvetkov, P., Chance, C., Smiley, S., Tutt, J., & Weber, C. (2012). Trains redesigned and incorporating nuclear systems (TRAINS). Transactions of the American Nuclear Society. 115-116. Rosaire, G., & Tsvetkov, P. (2012). A High Power-to-Weight Ratio Liquid Metal MHD Concept Reactor for Space and Terrestrial Needs Johns, J. M., & Tsvetkov, P. V. (2012). AUTONOMOUS CORIUM REACTOR FOR TERRESTRIAL APPLICATIONS. 667-680. Patel, V., & Tsvetkov, P. (2012). Integrated Multi-Modular Fast Reactor Concept Design. 713-724. Morota, H., Suzuki, H., Sakihama, T., Nasif, H. R., & Sano, H. (2012). Risk-Informed and Defense-in-Depth Oriented Plant Design Approach. 407-422. Cuvelier, M., & Tsvetkov, P. (2012). U-235 Prompt Neutron Fission Spectrum Data Sensitivity/Uncertainty Effects in Fuel Cycle Performance Parameters Johnson, M. P., Lewis, T. G., & Tsvetkov, P. V. (2011). 3D high-fidelity VHTR modeling for performance optimization simulations: Monitoring and operation. Transactions of the American Nuclear Society. 81-82. Tsvetkov, P. V., Bragg-Sitton, S. M., Johns, J. M., Lewis, T. G., Alajo, A. B., & Johnson, M. P. (2011). Distributed sensor networks for online 3D in-core monitoring in VHTR environments. Transactions of the American Nuclear Society. 931-933. Johns, J. M., Johnson, M. P., Tsvetkov, P. V., Bragg-Sitton, S. M., & Alajo, A. B. (2011). Emulation of VHTR operating conditions in TRIGA reactors. Transactions of the American Nuclear Society. 78-80. Tsvetkov, P., Chirayath, S., Ragusa, J., McDeavitt, S., Gariazzo, C., Johns, J., ... Rochau, G. E. (2011). High temperature super-critical CO2-cooled integrated multi-modular thermal reactor. Transactions of the American Nuclear Society. 1117-1119. Chirayath, S., Tsvetkov, P., Ragusa, J., Skoda, R., & Gariazzo, C. (2011). Methodology for public safety, proliferation, and economics assessment of SMRs. Transactions of the American Nuclear Society. 1078-1079. McIntyre, P., Sattarov, A., Tsvetkov, P., & Horak, W. (2011). Neutronics and heat transfer for an ADS Molten Salt Core. Transactions of the American Nuclear Society. 17-18. McIntyre, P., Sattarov, A., Tsvetkov, P., Horak, W., Simpson, M., & Phongikaroon, S. (2011). Pairing accelerator-driven subcritical power systems with conventional power stations, invited. Transactions of the American Nuclear Society. 890-891. Cuvelier, M., Ames, D. E., & Tsvetkov, P. V. (2011). Paramctric sensitivity/uncertainty effects in performance domain evaluations and design of advanced transmutation systems. Transactions of the American Nuclear Society. 686-687. Tsvetkov, P. V., Lewis, T. G., Lakshmipathy, S. K., Ougouag, A. M., & Venneri, F. (2011). Performance-constrained reload pattern searches for deep burn HTR hexagonal block systems. Transactions of the American Nuclear Society. 688-689. Jati, A. P., & Tsvetkov, P. (2011). Thorium fuel considerations for super-critical CO2-cooled integrated multi-modular thermal reactors. Transactions of the American Nuclear Society. 885-887. Tsvetkov, P., Ames, D. E., & Lewis III, T. G. (2011). Fidelity Needs for Safety, Performance and Fuel Cycle Evaluations in Integrated Simulations of Advanced Nuclear Energy Systems Ames, D. E., Tsvetkov, P. V., Rochau, G. E., & Rodriguez, S. (2010). High-fidelity integrated system modeling for sustainability analysis of nuclear energy systems. Transactions of the American Nuclear Society. 743-745. Kelly, R. P., Pritchard, M. L., & Tsvetkov, P. V. (2010). Pebble-bed system features and fuel utilization. Transactions of the American Nuclear Society. 579-580. Tsvetkov, P., Lewis III, T. G., Lakshmipathy, S. K., Ougouag, A. M., & Venneri, F. (2010). 3D Tracking in Reloading Optimization for Deep Burn HTR Hexagonal Block Systems Tsvetkov, P. V., & Guy, T. L. (2009). Architectures based on direct fission fragment energy conversion for interstellar exploration. 320-329. Tsvetkov, P. V. (2009). High-fidelity system modeling of advanced nuclear energy systems approaching a zero-nuclear-waste limit. 41-47. Ames, D. E., Tsvetkov, P. V., Rochau, G. E., & Rodriguez, S. (2009). Nuclear energy system providing an environmentally benign, sustainable, and secure energy source. Transactions of the American Nuclear Society. 177-178. Tsvetkov, P. V., Lewis, T. G., Ougouag, A. M., & Venneri, F. (2009). Reference basic cases and anticipated performance of DB-VHTRs in a single-path OTTO mode. Transactions of the American Nuclear Society. 248-250. Tsvetkov, P., & Alajo, A. B. (2009). Utilization of Transuranics as Fuel Component in VHTR Systems: The Back-End Considerations. 1886-1893. Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D. (2009). "USED FUEL" VECTORS AND WASTE MINIMIZATION STRATEGIES FOR VHTRs OPERATING WITHOUT REFUELING. 659-668. Tsvetkov, P. V., Alajo, A. B., & Ames, D. (2009). AUTONOMOUS CONTROL STRATEGIES FOR VHTR-BASED SYSTEMS FOR HYDROGEN PRODUCTION. 553-559. Ames, D., & Tsvetkov, P. V. (2009). BENCHMARK EFFORTS TO SUPPORT STUDIES OF ADVANCED VHTRs. 373-380. Tsvetkov, P. V., Ames, D., Alajo, A. B., & Lewis, T. (2009). VHTR-BASED SYSTEMS FOR AUTONOMOUS CO-GENERATION APPLICATIONS. 745-753. Tsvetkov, P., Vierow, K., Peddicord, K., Ragusa, J., McDeavitt, S., Poston, J., Shao, L., & Willems, G. (2008). Autonomous multi-purpose floating power system with a compact static pebble bed reactor. 1571-1576. Alajo, A., & Tsvetkov, P. (2008). Core lifetime and fuel utilization in prismatic VHTR cores. 1375-1380. Tsvetkov, P. V. (2008). LWR-VHTR fuel cycles with dedicated small 14mev waste incineration back-end clean-up facilities. Transactions of the American Nuclear Society. 220-221. Tsvetkov, P. V., Alajo, A. B., Lewis, T. G., & Ames, D. E. (2008). Out-of-core fuel cycle characteristics of VHTRs with no on-site refueling. 298-302. Alajo, A. B., & Tsvetkov, P. V. (2008). Reactor physics of VHTRs with UO2, UCO & UC 0.5O1.5 Kernels operating without onsite refueling. Transactions of the American Nuclear Society. 736-737. Sagdeev, R., Tsvetkov, P., Sadowski, W., Maldonado, G., Kritz, A., Gehin, J., ... DeHart, M. (2008). Development of a joint US-RF educational program in advanced energy technologies. Transactions of the American Nuclear Society. 775-776. Vierow, K., Best, F., Ford, J., Hassan, Y., McDeavitt, S., Ragusa, J., ... Tsvetkov, P. (2008). TAMU Nuclear safety curriculum development for a 21stcentury workforce. Transactions of the American Nuclear Society. 771-772. Tsvetkov, P. V., Lewis, T. G., & Alajo, A. B. (2008). Utilization of TRUs in VHTRs - Operation in a single-batch mode: Front end, back end, and performance. Transactions of the American Nuclear Society. 733-735. Tsvetkov, P. (2008). Analysis of Potential Fusion-Driven Power System Options and Applications. 138-138. Tsvetkov, P. V., Lewis, T., & Alajo, A. B. (2008). TRU-FUELED VHTRS FOR APPLICATIONS REQUIRING AN EXTENDED OPERATION WITH MINIMIZED CONTROL AND NO REFUELING. 331-338. Tsvetkov, P. V. (2007). Magnetic-nuclear propulsion/power system (MAGNUS): Control and heat removal options. 132-136. Lewis, T. G., Ames, D. E., & Tsvetkov, P. V. (2007). Analysis of TRU-fueled VHTR prismatic core performance Domains. Transactions of the American Nuclear Society. 859-860. Pritchard, M. L., Tsvetkov, P. V., & Alajo, A. B. (2007). Neutronics analysis of pebble-bed cores with TRUs. Transactions of the American Nuclear Society. 827-828. Bingham, A., Tsvetkov, P., & Cipiti, B. (2007). Parametric study to minimize radiation damage to reactor components in a pulsed subcritical fusion-fission hybrid system. Transactions of the American Nuclear Society. 779-780. Tsvetkov, P. V., Ames, D. E., Pritchard, M. L., Alajo, A. B., & Lewis, T. G. (2007). Tru-fueled VHTRs: Design, performance, and applications. 852-855. Tsvetkov, P. V., Ames, D. E., & Pritchard, M. L. (2007). Utilization of TRUs as a fuel for VHTRs: Compositions, neutronics impact and safety. Transactions of the American Nuclear Society. 769-770. Carter, J., Abrego, C., Guild-Bingham, A., Phinney, L., Hart, R., Tsvetkov, P., King, D. B., & Rochau, G. (2006). Direct energy conversion using he ion beams in support of the fission fragment magnetic collimator reactor experiment. Transactions of the American Nuclear Society. 99-100. Tsvetkov, P. V., Ames, D. E., Alajo, A. B., & Pritchard, M. L. (2006). Coupled hybrid Monte Carlo - Deterministic analysis of VHTR configurations with advanced actinide fuels. 1984-1990. Tsvetkov, P. V., & Hart, R. R. (2006). Direct fission fragment energy converter - Magnetic collimator option Pritchard, M. L., & Tsvetkov, P. V. (2006). Pebble-bed core design option for VHTRs - Core configuration flexibility and potential applications Tsvetkov, P. V., Ames, D. E., Alajo, A. B., & Pritchard, M. L. (2006). Self-sustainability of VHTR configurations with advanced actinide fuels Bingham, A., Tsvetkov, P., & Cipiti, B. (2006). Parametric Analysis of Z-Pinch Driven Nuclear Waste Incineration System Tsvetkov, P. V., Pritchard, M. L., Ames, D. E., & Alajo, A. B. (2006). Analysis of the pebble-bed VHTR spectrum shifting capabilities for advanced fuel cycles. Transactions of the American Nuclear Society. 403-404. Tsvetkov, P. V., Ames, D. E., & Alajo, A. B. (2006). Configuration adjustment potential of the VHTR prismatic cores with advanced actinide fuels. Transactions of the American Nuclear Society. 597-598. Tsvetkov, P. V., & Alajo, A. B. (2006). Potential of minor actinides to enhance VHTR performance characteristics. Transactions of the American Nuclear Society. 93-94. Tsvetkov, P. V., Hart, R. R., King, D. B., & Rochau, G. E. (2006). Planetary surface power and interstellar propulsion using fission fragment magnetic collimator reactor. AIP Conference Proceedings. 803-+. Tsvetkov, P. V., Ames, D. E., Pritchard, M. L., & Alajo, A. B. (2006). Spectrum Shifting as a Mechanism to Improve Performance of VHTRs with Advanced Actinide Fuels. 929-934. Tsvetkov, P. V., & Hart, R. R. (2005). Hybrid Monte Carlo - Deterministic analysis of the fission fragment magnetic collimator reactor systems. 1737-1745. Tsvetkov, P. V., & Hart, R. R. (2005). High efficiency magnetic-nuclear propulsion/power system. 749-754. King, D. B., Rochau, G. E., Oscar, D. S., Morrow, C. W., Tsvetkov, P. V., Hart, R. R., & Gallix, R. (2004). Experimental verification of magnetic insulation in direct energy conversion fission electric cells. Transactions of the American Nuclear Society. 929-930. Tsvetkov, P. V., Hart, R. R., & King, D. B. (2004). Fission fragment magnetic collimator reactor: Current status of the experimental program. Transactions of the American Nuclear Society. 927-928. Tsvetkov, P. V., & Hoogenboom, J. E. (2004). Reactivity effects in a HTGR due to variations of basic pebble-bed characteristics. Transactions of the American Nuclear Society. 559-560. King, D., Rochau, G., Oscar, D., Morrow, C., Tsvetkov, P., Hart, R., & Gallix, R. (2004). An Overview of the Direct Energy Conversion Proof of Principle Power Production Program. 551-555. Tsvetkov, P. V., Hart, R. R., & Parish, T. A. (2003). ICONE11-36275 HIGHLY EFFICIENT POWER SYSTEM BASED ON DIRECT FISSION FRAGMENT ENERGY CONVERSION UTILIZING MAGNETIC COLLIMATION. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 347-347. Tsvetkov, P. V., Hart, R. R., & Parish, T. A. (2003). Technological feasibility of fission fragment magnetic collimator reactors. Transactions of the American Nuclear Society. 582. Rochau, G., Cash, J., King, D., Morrow, C., Seidel, D., Slutz, S., ... Jordan, K. (2002). An Overview of the Direct Energy Conversion Power Production Program. 119-123. Tsvetkov, P. V., & Parish, T. A. (2002). Conceptual Analysis of Fission Fragment Magnetic Collimator Reactors. 23-29. patent Rhyne, S., & Tsvetkov, P. (2022). Integrated System for Converting Nuclear Energy into Electrical, Mechanical, and Thermal Energy and Methods for Using The Same Rosaire IV, C., & Tsvetkov, P. (2018). Solid State Direct Nuclear Energy Converter Utilizing Subatomic Energy Yield report Tsvetkov, P., & Hart, R. R. (2005). Experimental Verification of Magnetic Insulation for Direct Energy Conversion Fission Reactors: Year Three (Final) Activities Report
editor of book Tsvetkov, P. (2018). Energy Systems and Environment Tsvetkov, P. (Eds.), BoD Books on Demand. Waltar, A. E., Todd, D. R., & Tsvetkov, P. V. (2011). Fast Spectrum Reactors Tsvetkov, P. V. (Eds.), Springer. Tsvetkov, P. (2011). Nuclear Power Control, Reliability and Human Factors Tsvetkov, P. (Eds.), IntechOpen. Tsvetkov, P. (2011). Nuclear Power Deployment, Operation and Sustainability Tsvetkov, P. (Eds.), IntechOpen. Tsvetkov, P. (2011). Nuclear Power Operation, Safety and Environment Tsvetkov, P. (Eds.), IntechOpen. Tsvetkov, P. (2011). Nuclear Power System Simulations and Operation Tsvetkov, P. (Eds.), IntechOpen. Tsvetkov, P. (2010). Nuclear Power Tsvetkov, P. (Eds.), IntechOpen.
co-principal investigator on NuSTEM: Nuclear Science, Technology and Education for Molten Salt Reactors awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2017 - 2020
teaching activities ENGR385 Prob For Coop Students Instructor ENGR684 Professional Internship: In-ab Instructor ENGR684 Professional Internship: In-ab Instructor FIVS491 Research Instructor ITDE691 Research Instructor NUEN301 Nuclear Reactor Theory Instructor NUEN302 Intro To Nuen Ii Instructor NUEN304 Nuclear Reactor Analysis Instructor NUEN460 Nuc Plant Sys And Tran Instructor NUEN485 Directed Studies Instructor NUEN491 Hnr-research Instructor NUEN601 Nuclear Reactor Theory Instructor NUEN604 Rad Interact & Shield Instructor NUEN608 Fst Spctrm Sys Instructor NUEN610 Nuclear Reactor Des Instructor NUEN621 Nuclear Crit Safety Fundmtls Instructor NUEN684 Professional Internship: In-ab Instructor NUEN685 Directed Studies Instructor NUEN685 Directed Studies Instructor NUEN689 Sptp:nuc Crit Safe Fund Instructor NUEN689 Sptp:nuclear Crit Safety Fund Instructor NUEN691 Research Instructor NUEN691 Research: In-ab Instructor
chaired theses and dissertations Al Rashdan, Ahmad Y. M. (2014-12). Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions. Alajo, Ayodeji Babatunde (2007-12). Impact of PWR spent fuel variations on TRU-fueled VHTRS. Alajo, Ayodeji Babatunde (2010-05). Fission Product Impact Reduction via Protracted In-core Retention in Very High Temperature Reactor (VHTR) Transmutation Scenarios. Ames, David E, II (2006-08). Configuration adjustment potential of the Very High Temperature Reactor prismatic cores with advanced actinide fuels. Ames, David E. (2010-08). High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source. Cuvelier, Marie-Hermine (2012-05). Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties. Guy, Troy Lamar (2009-12). Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications. Hearne, Jason A (2015-04). Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator. Honang, Hanniel Jouvain (2016-04). Reactor Physics Analysis of Air-Cooled Nuclear System. Johns, Jesse Merlin (2014-12). Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations. Johnson, Matthew Paul (2013-04). Application of Next-Generation Sensor Systems in HTRs. Kelly, Ryan Patrick (2013-05). Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. Kumar, Akansha (2016-12). An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. Lakshmipathy, Sathish Kumar (2012-05). VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D. Leimon, Michael 1985- (2012-11). Coupling Interface for Physics-to-System Simulations. Lewis, Tom Goslee (2007-12). Analysis of tru-fueled vhtr prismatic core performance domains. Lewis, Tom Goslee, III (2010-08). Physics-Based 3D Multi-Directional Reloading Algorithm for Deep Burn HTR Prismatic Block Systems. Mathis, Dean (2014-04). Design Options for Ultra-compact Nuclear Driven Power Sources for Field Applications. Metcalf, Richard (2011-12). Safeguards Envelope Methodology. Patel, Vishal (2012-07). A Multi-Modular Neutronically Coupled Power Generation System. Pritchard, Megan L (2014-05). Characterization Methodology for Decommissioning Low and Intermediate Level Fissile Nuclide Contaminated Buried Soils and Process Piping Using Photon Counting. Pritchard, Megan Leigh (2007-12). Neutronic analysis of pebble-bed cores with transuranics. Redwine, Adam B. (2010-08). Impact of Climate Change on Long Term Nuclear Power Plant Operation. Rosaire IV, Carol Gwyn (2016-05). Anisotropic Neutron Imaging. Scherr, Jonathan B (2016-04). Fast Spectrum Material's Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D. Scherr, Jonathan B (2018-08). A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints. Stratton, Charles David (2019-04). 3D Power Profile Reconstruction Using Distributed Sensing Fiber Optics. Worn, Cheyn (2012-05). An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection. Yancey, Kristina (2013-11). Nationwide Used Fuel Inventory Analysis.
education and training Ph.D. in Nuclear Engineering, Texas A&M University - (College Station, Texas, United States) 2002 M.S. in Nuclear Engineering, Moscow Engineering Physics Institute - (Moscow, Russia) 1995
mailing address Texas A&M University Nuclear Engineering 3133 TAMU College Station, TX 77843-3133 USA