HR job title
- Professor
- Contact Info
- 1 979 845 7078
Tsvetkov, Pavel Associate Professor
Positions
- Associate Professor, Nuclear Engineering, College of Engineering
- Faculty Affiliate, Institute for Engineering Education and Innovation, Texas A&M Engineering Experiment Station (TEES)
- Faculty Affiliate, Energy Institute, Texas A&M Engineering Experiment Station (TEES)
I strive to establish a diversified externally-sponsored research program focused on design, analysis and assessment of next generation nuclear systems for terrestrial and space applications.
- Overview
- Publications
- Research
- Teaching
- Works By Students
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Overview
Publications
selected publications
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academicarticle
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Rashdan, A. A., & Tsvetkov, P.
(2012).
Hierarchical Integrated Parameters Exploration in Systems Modeling. 99(1), 1-13.
-
Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D.
"Used fuel" vectors and waste minimization strategies for VHTRS operating without refueling. Nuclear Engineering and Design.
240(10), 2458-2465.
-
Weiss, A. G., Aranguren, B., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M.
A Data-driven approach to predicting neutron penetration through media. Annals of Nuclear Energy.
192, 109953-109953.
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Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J.
A greedy memetic algorithm for a multiobjective dynamic bin packing problem for storing cooling objects. Journal of Heuristics.
25(1), 1-45.
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Mueller, C., & Tsvetkov, P.
A network approach to full core temperature analysis in advanced nuclear heat-pipe systems. Annals of Nuclear Energy.
160, 108354-108354.
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Kumar, A., & Tsvetkov, P. V.
A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis. Annals of Nuclear Energy.
85, 27-35.
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Weiss, A. G., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M.
A novel method for the design and selection of neutron-attenuating media. Annals of Nuclear Energy.
160, 108368-108368.
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Mueller, C., & Tsvetkov, P.
A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis. Annals of Nuclear Energy.
160, 108393-108393.
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Weiss, A. G., V. Tsvetkov, P., Hearne, J., Kimber, M. L., Wootan, D. W., & McDeavitt, S. M.
A sensitivity analysis to predict the neutronics behavior of samples irradiated in the VTR rabbit system. Annals of Nuclear Energy.
185, 109708-109708.
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Mendoza, M., & Tsvetkov, P. V.
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Fault diagnosis. PROGRESS IN NUCLEAR ENERGY.
168, 104989-104989.
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Mendoza, M., & V. Tsvetkov, P.
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Power transient identification. PROGRESS IN NUCLEAR ENERGY.
156.
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Mendoza, M., & Tsvetkov, P. V.
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Unknown fault detection. PROGRESS IN NUCLEAR ENERGY.
171, 105167-105167.
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Patel, V., Navarro, J., Windes, W., & Tsvetkov, P.
An uncertainty quantification method relevant to material test reactors. Annals of Nuclear Energy.
165, 108629-108629.
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Kumar, A., Chirayath, S. S., & Tsvetkov, P. V.
Analysis of a sustainable gas cooled fast breeder reactor concept. Annals of Nuclear Energy.
69, 252-259.
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Hearne, J. A., & Tsvetkov, P. V.
Analysis of the transmutation of long lived fission products using a charged particle beam. Annals of Nuclear Energy.
133, 501-510.
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Tsvetkov, P. V., Alajo, A. B., & Ames, D.
Autonomous Control Strategies for Very High Temperature Reactor Based Systems for Hydrogen Production. Journal of Engineering for Gas Turbines and Power.
131(5), 052906.
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Ganapol, B., & Tsvetkov, P.
CHAPTER 5 DIFFUSION THEORY. EPJ Web of Conferences.
247, 14005-14005.
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Valko, J., Tsvetkov, P. V., & Hoogenboom, J. E.
Calculation of the Dancoff factor for pebble bed reactors. Nuclear Science and Engineering.
135(3), 304-307.
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McDeavitt, S. M., Wootan, D., Kimber, M., Kirkland, K. V., Ortega, L. H., Perez-Nunez, D., ... Woolstenhulme, N. E.
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies. Nuclear Science and Engineering.
197(11), 2840-2852.
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Patel, V., & Tsvetkov, P.
Concept of a high temperature integrated multi-modular thermal reactor. Annals of Nuclear Energy.
55, 312-321.
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Passons, B., & Tsvetkov, P.
Design and performance analysis of a mobile, land-based micro-reactor. Annals of Nuclear Energy.
165, 108688-108688.
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Scherr, J., & Tsvetkov, P.
Design strategies for LWR and VHTR test environments in a fast spectrum reactor. Annals of Nuclear Energy.
120, 219-235.
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Abuqudaira, T., Tsvetkov, P., & Sabharwall, P.
Dynamics of Molten Salt Reactor with Operating Heaters. Nuclear Science and Engineering.
ahead-of-print(ahead-of-print), 1-22.
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Clarno, K. T., Barlow, J. E., Sawyer, T., Scherr, J., Hearne, J., & Tsvetkov, P.
Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark. Annals of Nuclear Energy.
194, 110092-110092.
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Stratton, C., & Tsvetkov, P.
Experimental analysis of fiber optic responses in ionizing radiation environments for distributed sensing applications. PROGRESS IN NUCLEAR ENERGY.
130, 103519-103519.
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Watson, D., Gatchalian, R., Hsieh, H., Bhat, P., & Tsvetkov, P. V.
Fission Surface PowerA Conceptual 350-kW(thermal) Microreactor Designed for Lunar Power Around SpaceX Falcon Heavy Mass Constraints. Nuclear Technology.
1-13.
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Ames, D., & Tsvetkov, P. V.
High-fidelity system modeling of advanced nuclear energy systems approaching a zero-nuclear-waste limit. PROGRESS IN NUCLEAR ENERGY.
53(6), 626-632.
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Alajo, A. B., & Tsvetkov, P. V.
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.
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Kumar, A., Tsvetkov, P. V., & McClarren, R. G.
Linear regression and sensitivity analysis in nuclear reactor design. Annals of Nuclear Energy.
85, 798-811.
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Mendoza, M., Tsvetkov, P. V., & Lewis, M.
Multi-modal global surveillance methodology for predictive and on-demand characterization of localized processes using cube satellite platforms and deep learning techniques. Remote Sensing Applications: Society and Environment.
22, 100518-100518.
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Patel, V., & Tsvetkov, P.
Multi-module approach to modularity in a neutronically coupled high temperature multi-modular system. Nuclear Engineering and Design.
263, 411-418.
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Luan, X., & Tsvetkov, P. V.
Novel consistent approach in controllability evaluations of point reactor kinetics models. Annals of Nuclear Energy.
131, 496-506.
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Mueller, C., & Tsvetkov, P.
Novel design integration for advanced nuclear heat-pipe systems. Annals of Nuclear Energy.
141, 107324-107324.
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Kumar, A., & Tsvetkov, P. V.
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.
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Spencer, K. Y., Tsvetkov, P. V., & Jarrell, J. J.
Optimization of dry cask loadings for used nuclear fuel management strategies. PROGRESS IN NUCLEAR ENERGY.
108, 11-25.
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Al Rashdan, A., & Tsvetkov, P.
Parametric evaluation of an SMR design domain. Annals of Nuclear Energy.
85, 958-978.
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Hearne, J. A., & Tsvetkov, P. V.
Physical anomaly detection and identification using Cerenkov radiation. Annals of Nuclear Energy.
142, 107424-107424.
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Lewis, T., & Tsvetkov, P. V.
Physics Features of TRU-Fueled VHTRs. Science and Technology of Nuclear Installations.
2009(1),
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Hearne, J. A., & Tsvetkov, P. V.
Power Profile Reconstruction and Anomaly Detection Approach for FHRs Using Cerenkov Radiation. Nuclear Technology.
206(11), 1740-1750.
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Connolly, K. J., Rahnema, F., & Tsvetkov, P. V.
Prismatic VHTR neutronic benchmark problems. Nuclear Engineering and Design.
285, 207-240.
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Yancey, K., & Tsvetkov, P. V.
Quantification of US spent fuel inventories in nuclear waste management. Annals of Nuclear Energy.
72, 277-285.
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Gatchalian, R., & Tsvetkov, P. V.
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks. Nuclear Science and Engineering.
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Scherr, J., & Tsvetkov, P.
Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor. Annals of Nuclear Energy.
113, 15-24.
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Gatchalian, R., & Tsvetkov, P. V.
Reactor physics analysis of a Source-driven TRIGA configuration in subcritical domain. Annals of Nuclear Energy.
186, 109787-109787.
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Hearne, J. A., & Tsvetkov, P. V.
Response function generation for Cerenkov radiation production and transport in a TRIGA coolant channel. Annals of Nuclear Energy.
138, 107200-107200.
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Scherr, J., & Tsvetkov, P.
Scoping Studies of Reactor Core Parameters in Support of the Abilene Christian University Molten Salt Research Reactor. Nuclear Technology.
209(11), 1733-1746.
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Hearne, J. A., & Tsvetkov, P. V.
Spatial power profiling method using visual information in reactors with optically transparent coolants. Annals of Nuclear Energy.
137, 107071-107071.
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Tsvetkov, P. V., Ames, D., Alajo, A. B., & Lewis, T.
Spectrum shifting as a mechanism to improve performance of VHTRs with advanced actinide fuels. Nuclear Engineering and Design.
238(8), 1958-1964.
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Cuvelier, M., & Tsvetkov, P. V.
TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs. Annals of Nuclear Energy.
55, 137-150.
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Tsvetkov, P. V., Lewis, T., & Alajo, A. B.
TRU-Fueled Very High Temperature Reactors for Applications Requiring an Extended Operation With Minimized Control and No Refueling. Journal of Engineering for Gas Turbines and Power.
131(5), 052907.
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Gates, J. T., & Tsvetkov, P. V.
Testing of fiber optic based sensors for advanced reactors in the Texas A&M University TRIGA reactor. Annals of Nuclear Energy.
196, 110222-110222.
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Hearne, J. A., & Tsvetkov, P. V.
Three dimensional reactor power profile reconstruction using Cerenkov radiation. Annals of Nuclear Energy.
142, 107426-107426.
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Gatchalian, R., & Tsvetkov, P. V.
Traditional machine learning methods in predicting the physics of subcritical systems in source-equilibrium. Annals of Nuclear Energy.
201, 110413-110413.
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Kelly, R., Tsvetkov, P., Chirayath, S., Poston, J., & Kitcher, E.
UNCERTAINTY QUANTIFICATION OF CONCRETE UTILIZED IN DRY CASK STORAGE. Nuclear Technology.
190(1), 72-87.
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Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D.
VHTR-based systems for autonomous co-generation applications. Nuclear Engineering and Design.
240(10), 2451-2457.
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Spencer, K. Y., Tsvetkov, P. V., & Janell, J. J.
Validation of the GAMMA-PC methodology for dry cask loading optimization. PROGRESS IN NUCLEAR ENERGY.
117, 103038-103038.
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Yancey, K., & Tsvetkov, P. V.
Variability in spent fuel inventory data. PROGRESS IN NUCLEAR ENERGY.
81, 184-195.
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Stolte, K. N., & V. Tsvetkov, P.
x-MeRA: Computationally efficient adaptive mesh refinement of Monte Carlo mesh based tallies. Annals of Nuclear Energy.
182.
-
Rashdan, A. A., & Tsvetkov, P.
(2012).
Hierarchical Integrated Parameters Exploration in Systems Modeling. 99(1), 1-13.
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book
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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.
-
Tsvetkov, P.
Nuclear Fission From Fundamentals to Applications. BoD Books on Demand.
-
Pioro, I.
(2016).
Handbook of Generation IV Nuclear Reactors. Woodhead Publishing.
-
chapter
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Waltar, A., Todd, D., & Tsvetkov, P.
(2011).
Fast Reactor Simulations. Fast Spectrum Reactors.
Springer.
-
Tsvetkov, P., & Guy, T.
(2010).
Advanced Magnetic-Nuclear Power Systems for Reliability Demanding Applications Including Deep Space Missions. Nuclear Power.
IntechOpen.
-
Tsvetkov, P. V.
Basic Concepts of Nuclear Fission. Nuclear Energy Encyclopedia.
(pp. 45-49).
Wiley.
-
Tsvetkov, P.
Chapter 4 Gas-cooled Fast Reactors (GFRs). Handbook of Generation IV Nuclear Reactors.
(pp. 167-172).
Elsevier.
-
Tsvetkov, P.
Chapter 9 Generation IV: United States. Handbook of Generation IV Nuclear Reactors.
(pp. 287-301).
Elsevier.
-
Tsvetkov, P. V.
Direct Energy Conversion Concepts. Nuclear Energy Encyclopedia.
(pp. 569-579).
Wiley.
-
Tsvetkov, P. V., & Ames, D. E.
Electrical Generation from Nuclear Power Plants. Nuclear Energy Encyclopedia.
(pp. 57-64).
Wiley.
-
Tsvetkov, P. V.
Fission Energy Usage: Status, Trends and Applications. Nuclear Energy Encyclopedia.
(pp. 159-163).
Wiley.
-
Tsvetkov, P., Waltar, A., & Salvatores, M.
Fuel Management. Fast Spectrum Reactors.
(pp. 135-185).
Springer Nature.
-
Tsvetkov, P.
Gas-cooled fast reactors. Handbook of Generation IV Nuclear Reactors.
(pp. 91-96).
-
Tsvetkov, P.
Generation IV: USA. Handbook of Generation IV Nuclear Reactors.
(pp. 223-239).
-
Tsvetkov, P. V.
GraphiteModerated Fission Reactor Technology. Nuclear Energy Encyclopedia.
(pp. 187-192).
Wiley.
-
Tsvetkov, P., Waltar, A., & Todd, D.
Introductory Design Considerations. Fast Spectrum Reactors.
(pp. 23-38).
Springer Nature.
-
Tsvetkov, P., Waltar, A., & Todd, D.
Kinetics, Reactivity Effects, and Control Requirements. Fast Spectrum Reactors.
(pp. 111-133).
Springer Nature.
-
Tsvetkov, P. V.
Management of the Nuclear Waste Via Disposition or Transmutation. Encyclopedia of Nuclear Energy.
(pp. 465-477).
Elsevier.
-
Tsvetkov, P., & Waltar, A.
Nuclear Data and Cross Section Processing. Fast Spectrum Reactors.
(pp. 77-109).
Springer Nature.
-
Tsvetkov, P., Waltar, A., & Todd, D.
Nuclear Design. Fast Spectrum Reactors.
(pp. 49-76).
Springer Nature.
-
Abuqudaira, T., Tsvetkov, P., & Sabharwall, P.
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. V., & Stachowski, R. E.
Physics of the Fission Chain Reaction in Thermal and Fast Reactors. Encyclopedia of Nuclear Energy.
(pp. 172-186).
Elsevier.
-
Tsvetkov, P., Waltar, A., & Todd, D.
Reactor Plant Systems. Fast Spectrum Reactors.
(pp. 365-407).
Springer Nature.
-
Tsvetkov, P., Waltar, A., & Todd, D.
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.
-
conference paper
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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).
Neutronics/Thermal-Hydraulics Coupling in Simulation of Advanced Nuclear Reactors
-
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
-
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.
-
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.
-
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 CO
2 -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 CO
2 -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., 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 UO
2 , UCO & UC0.5 O1.5 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.
(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.
(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.
-
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.
-
Tsvetkov, P. V., Lewis, T., Alajo, A. B., & Ames, D.
"USED FUEL" VECTORS AND WASTE MINIMIZATION STRATEGIES FOR VHTRs OPERATING WITHOUT REFUELING. 659-668.
-
Biegalski, S., Tsvetkov, P., Tao, Y., Sobes, V., Pazdernik, K., Labov, S., ... Hero, A.
2020 ETI Annual Summer School: Data Science and Engineering
-
Ndum, Z. N., Tao, J., Liu, Y., Ford, J., Vlassov, V., Morton, N., ... Adu, S.
A Digital Twin-Based Simulator for Small Modular and Microreactors
-
Rosaire, G., & Tsvetkov, P.
A High Power-to-Weight Ratio Liquid Metal MHD Concept Reactor for Space and Terrestrial Needs
-
Tsvetkov, P. V., Alajo, A. B., & Ames, D.
AUTONOMOUS CONTROL STRATEGIES FOR VHTR-BASED SYSTEMS FOR HYDROGEN PRODUCTION. 553-559.
-
Johns, J. M., & Tsvetkov, P. V.
AUTONOMOUS CORIUM REACTOR FOR TERRESTRIAL APPLICATIONS. 667-680.
-
McIntyre, P., Assadi, S., Badgley, K., Baker, W., Comeaux, J., Gerity, J., ... Tsvetkov, P.
Accelerator-Driven Subcritical Fission In Molten Salt Core: Closing The Nuclear Fuel Cycle For Green Nuclear Energy. AIP Conference Proceedings.
636-642.
-
Rochau, G., Cash, J., King, D., Morrow, C., Seidel, D., Slutz, S., ... Jordan, K.
An Overview of the Direct Energy Conversion Power Production Program. 119-123.
-
King, D., Rochau, G., Oscar, D., Morrow, C., Tsvetkov, P., Hart, R., & Gallix, R.
An Overview of the Direct Energy Conversion Proof of Principle Power Production Program. 551-555.
-
Hearne, J., McDeavitt, S., Scherr, J., Tsvetkov, P., & Wootan, D.
Analysis of the VTR In-Core Environment with the Rabbit Delivery System Enabling Encapsulated Irradiations. 1427-1430.
-
Ames, D., & Tsvetkov, P. V.
BENCHMARK EFFORTS TO SUPPORT STUDIES OF ADVANCED VHTRs. 373-380.
-
Tsvetkov, P. V., & Parish, T. A.
Conceptual Analysis of Fission Fragment Magnetic Collimator Reactors. 23-29.
-
McDeavitt, S., Kimber, M., Kirkland, K., Ortega, L., Perez-Nunez, D., Tsvetkov, P., ... Weiss, A.
Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor. 1408-1411.
-
Abuqudaira, T., zen, . ., Dean, D., Tsvetkov, P., & Sabharwall, P.
Dynamics and Stability Analysis Study of a Thermal Molten Salt Reactor. 2387-2396.
-
Abuqudaira, T., Tsvetkov, P., & Sabharwall, P.
Exploring the Effect of the Number of Groups of Delayed Neutron Precursors in Reactor Dynamics Simulations of Molten Salt Reactors. Transactions of the American Nuclear Society.
1068-1071.
-
Hsieh, H. Y., Abuqudaira, T., Tsvetkov, P., & Sabharwall, P.
Feasibility of Remote Monitoring of Microreactors Using Satellites and Leveraging Transfer Learning and Pre-trained Models. Transactions of the American Nuclear Society.
908-911.
-
Abuqudaira, T., Tsvetkov, P., & Sabharwall, P.
Fuel Flow Modeling Under Thermal Fluidics Considerations Within Operational Domains of Molten Salt Reactors. 3208-3221.
-
Tsvetkov, P. V., Hart, R. R., & Parish, T. A.
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.
-
Patel, V., & Tsvetkov, P.
Integrated Multi-Modular Fast Reactor Concept Design. 713-724.
-
Sattarov, A., Assadi, S., Badgley, K., Baty, A., Comeaux, J., Gerity, J., ... Mann, T.
Neutronics of accelerator-driven subcritical fission for burning transuranics in used nuclear fuel. AIP Conference Proceedings.
245-250.
-
Tsvetkov, P. V., Hart, R. R., King, D. B., & Rochau, G. E.
Planetary surface power and interstellar propulsion using fission fragment magnetic collimator reactor. AIP Conference Proceedings.
803-+.
-
Morota, H., Suzuki, H., Sakihama, T., Nasif, H. R., & Sano, H.
Risk-Informed and Defense-in-Depth Oriented Plant Design Approach. 407-422.
-
Watson, D., Gatchalian, R. D., Hsieh, H., Bhat, P., & Tsvetkov, P.
SpaceX Falcon Heavy Mass Constraints as Design Driver for Practical Heat Pipe Stirling Micro Reactors. 305-311.
-
Tsvetkov, P. V., Ames, D. E., Pritchard, M. L., & Alajo, A. B.
Spectrum Shifting as a Mechanism to Improve Performance of VHTRs with Advanced Actinide Fuels. 929-934.
-
Tsvetkov, P. V., Lewis, T., & Alajo, A. B.
TRU-FUELED VHTRS FOR APPLICATIONS REQUIRING AN EXTENDED OPERATION WITH MINIMIZED CONTROL AND NO REFUELING. 331-338.
-
Cuvelier, M., & Tsvetkov, P.
U-235 Prompt Neutron Fission Spectrum Data Sensitivity/Uncertainty Effects in Fuel Cycle Performance Parameters
-
Tsvetkov, P. V., Ames, D., Alajo, A. B., & Lewis, T.
VHTR-BASED SYSTEMS FOR AUTONOMOUS CO-GENERATION APPLICATIONS. 745-753.
-
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.
-
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
-
Scherr, J., Head, T., Haas, D., Shoemate, J., Tsvetkov, P., & Towell, R.
Gas management systems for a molten salt nuclear reactor (patent pending)
-
Rhyne, S., & Tsvetkov, P.
(2022).
Integrated System for Converting Nuclear Energy into Electrical, Mechanical, and Thermal Energy and Methods for Using The Same
-
report
-
Tsvetkov, P., & Hart, R. R.
(2005).
Experimental Verification of Magnetic Insulation for Direct Energy Conversion Fission Reactors: Year Three (Final) Activities 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.
-
Tsvetkov, P.
(2018).
Energy Systems and Environment
Tsvetkov, P. (Eds.),
BoD Books on Demand.
Research
co-principal investigator on
Teaching
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
Works By Students
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.
Background
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
Contact
first name
- Pavel
has last name
- Tsvetkov
mailing address
-
Texas A&M University
Nuclear Engineering
3133 TAMU
College Station, TX 77843-3133
USA
Other
In the News
- tsvetkov@tamu.edu