Theodore M. Besmann
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Research Subjects
Theodore M. Besmann has a total of 77 co-authors. Here are the top co-authors by number of shared publications:
- Hans-Conrad Zur Loye
Department of Chemistry and Biochemistry, University of South Carolina, Columbia, USA
6 shared publications - Juliano Schorne-Pinto
University of South Carolina
5 shared publications - Vancho Kocevski
Department of Mechanical Engineering, University of South Carolina, Columbia, South Carolina 29208, United States
5 shared publications Amir M. Mofrad
University of South Carolina
3 shared publications- Gregory Morrison
University of South Carolina
3 shared publications - Christian A. Juillerat
Department of Chemistry and Biochemistry
2 shared publications
Latest Publications
- 30 April 2026
- Published by Taylor & Francis in Nuclear Science and Engineering
- p. 1-24
Thermodynamic Assessment of the Na,K,Cs|Cl,I Reciprocal Salt for Chloride-Fueled MSR Accident Analysis
I. To accurately simulate a salt-fueled molten salt reactor (MSR) [1,2] under operating conditions or off-normal conditions, it is necessary to represent the thermochemical behavior of fission prod...
- 30 April 2026
- Published by Taylor & Francis in Nuclear Science and Engineering
- p. 1-24
Thermodynamic Assessment of the Na,K,Cs|Cl,I Reciprocal Salt for Chloride-Fueled MSR Accident Analysis
I. To accurately simulate a salt-fueled molten salt reactor (MSR) [1,2] under operating conditions or off-normal conditions, it is necessary to represent the thermochemical behavior of fission prod...
- 19 April 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 629
Thermodynamic properties of uranium-zirconium carbide solid solutions with oxygen
- 19 April 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 629
Thermodynamic properties of uranium-zirconium carbide solid solutions with oxygen
- 4 June 2025
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 615
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt
- 4 June 2025
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 615
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt
- Open Access
- 21 March 2025
- Published by American Association for the Advancement of Science (AAAS) in Science Advances
- Vol. 11 (12) , eadt3518
A low-temperature, one-step synthesis for monazite can transform monazite into a readily usable advanced nuclear waste form
It has been demonstrated that monazite-type materials are excellent candidates for nuclear waste forms, and hence, their facile synthesis is of great importance for the needed sequestration of existing nuclear waste. The synthesis of monazite, LaPO 4 , requires inconveniently high temperatures near 1000°C and generally involves the conversion of the presynthesized rhabdophane, LaPO 4 •nH 2 O, to the LaPO 4 monazite phase. During this structure transformation, the rhabdophane converts irreversibly to the thermodynamically stable monoclinic monazite structure. A low-temperature (185° to 260°C) mild hydrothermal acid-promoted synthesis of monazite is described that can both transform presynthesized rhabdophane or assemble reagents to the monoclinic monazite structure. The pH dependence of this reaction is detailed, and its applicability to the Ln PO 4 ( Ln = La, Ce, Pr, Nd, Sm-Gd), Ca 0.5 Th 0.5 PO 4 , and Sr 0.5 Th 0.5 PO 4 systems is discussed. The crystal growth of Ca 0.5 Th 0.5 PO 4 and Sr 0.5 Th 0.5 PO 4 is described, and their crystal structures were reported. In situ x-ray diffraction studies, performed as a function of temperature, provide insight into the structure transformation process.
- 21 March 2025
- Published by American Association for the Advancement of Science (AAAS) in Science Advances
- Vol. 11 (12) , eadt3518
Open AccessA low-temperature, one-step synthesis for monazite can transform monazite into a readily usable advanced nuclear waste form
It has been demonstrated that monazite-type materials are excellent candidates for nuclear waste forms, and hence, their facile synthesis is of great importance for the needed sequestration of existing nuclear waste. The synthesis of monazite, LaPO 4 , requires inconveniently high temperatures near 1000°C and generally involves the conversion of the presynthesized rhabdophane, LaPO 4 •nH 2 O, to the LaPO 4 monazite phase. During this structure transformation, the rhabdophane converts irreversibly to the thermodynamically stable monoclinic monazite structure. A low-temperature (185° to 260°C) mild hydrothermal acid-promoted synthesis of monazite is described that can both transform presynthesized rhabdophane or assemble reagents to the monoclinic monazite structure. The pH dependence of this reaction is detailed, and its applicability to the Ln PO 4 ( Ln = La, Ce, Pr, Nd, Sm-Gd), Ca 0.5 Th 0.5 PO 4 , and Sr 0.5 Th 0.5 PO 4 systems is discussed. The crystal growth of Ca 0.5 Th 0.5 PO 4 and Sr 0.5 Th 0.5 PO 4 is described, and their crystal structures were reported. In situ x-ray diffraction studies, performed as a function of temperature, provide insight into the structure transformation process.
- 14 July 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 600
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations
- 14 July 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 600
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations
- Open Access
Applications of Thermochemical Modeling in Molten Salt Reactors
The extensively evaluated and consistent thermodynamic database, the Molten Salt Thermal Properties Database—Thermochemical (MSTDB-TC), was used along with additional thermodynamic values from other sources as examples of ways to examine molten salt reactor (MSR) fuel behavior. Relative stability with respect to halide potential and temperature for likely fuel and fission product components were mapped in Ellingham diagrams for the chloride and fluoride systems. The Ellingham diagrams provide a rich, visual means for identifying halide-forming components in proposed fuel/solvent salt systems. Thermochemical models and values from MSTDB-TC and ancillary sources were used in global equilibrium calculations to provide compositions for a close analysis of the behavior of a possible Molten Chloride Salt Fast Reactor and a Molten Salt Reactor Experiment-type system at high burnup (100 GWd/t). The results illustrated the oxidative nature of burnup in MSRs and provided information about redox behavior and possible control.
Open AccessApplications of Thermochemical Modeling in Molten Salt Reactors
The extensively evaluated and consistent thermodynamic database, the Molten Salt Thermal Properties Database—Thermochemical (MSTDB-TC), was used along with additional thermodynamic values from other sources as examples of ways to examine molten salt reactor (MSR) fuel behavior. Relative stability with respect to halide potential and temperature for likely fuel and fission product components were mapped in Ellingham diagrams for the chloride and fluoride systems. The Ellingham diagrams provide a rich, visual means for identifying halide-forming components in proposed fuel/solvent salt systems. Thermochemical models and values from MSTDB-TC and ancillary sources were used in global equilibrium calculations to provide compositions for a close analysis of the behavior of a possible Molten Chloride Salt Fast Reactor and a Molten Salt Reactor Experiment-type system at high burnup (100 GWd/t). The results illustrated the oxidative nature of burnup in MSRs and provided information about redox behavior and possible control.
- Open Access
- 16 June 2022
- Published by MDPI AG in Inorganics
- Vol. 10 (6) , 83
Luminescence and Scintillation in the Niobium Doped Oxyfluoride Rb4Ge5O9F6:Nb
A new niobium-doped inorganic scintillating oxyfluoride, Rb4Ge5O9F6:Nb, was synthesized in single crystal form by high-temperature flux growth. The host structure, Rb4Ge5O9F6, crystallizes in the orthorhombic space group Pbcn with lattice parameters a = 6.98430(10) Å, b = 11.7265(2) Å, and c = 19.2732(3) Å, consisting of germanium oxyfluoride layers made up of Ge3O9 units connected by GeO3F3 octahedra. In its pure form, Rb4Ge5O9F6 shows neither luminescence nor scintillation but when doped with niobium, Rb4Ge5O9F6:Nb exhibits bright blue luminescence and scintillation. The isostructural doped structure, Rb4Ge5O9F6:Nb, crystallizes in the orthorhombic space group Pbcn with lattice parameters a = 6.9960(3) Å, b = 11.7464(6) Å, and c = 19.3341(9) Å. X-ray absorption near edge structure (XANES) and extended X-ray absorption fine structure (EXAFS) measurements suggest that the niobium is located in an octahedral coordination environment. Optical measurements inform us that the niobium dopant acts as the activator. The synthesis, structure, and optical properties are reported, including radioluminescence (RL) measurements under X-ray irradiation.
- 16 June 2022
- Published by MDPI AG in Inorganics
- Vol. 10 (6) , 83
Open AccessLuminescence and Scintillation in the Niobium Doped Oxyfluoride Rb4Ge5O9F6:Nb
A new niobium-doped inorganic scintillating oxyfluoride, Rb4Ge5O9F6:Nb, was synthesized in single crystal form by high-temperature flux growth. The host structure, Rb4Ge5O9F6, crystallizes in the orthorhombic space group Pbcn with lattice parameters a = 6.98430(10) Å, b = 11.7265(2) Å, and c = 19.2732(3) Å, consisting of germanium oxyfluoride layers made up of Ge3O9 units connected by GeO3F3 octahedra. In its pure form, Rb4Ge5O9F6 shows neither luminescence nor scintillation but when doped with niobium, Rb4Ge5O9F6:Nb exhibits bright blue luminescence and scintillation. The isostructural doped structure, Rb4Ge5O9F6:Nb, crystallizes in the orthorhombic space group Pbcn with lattice parameters a = 6.9960(3) Å, b = 11.7464(6) Å, and c = 19.3341(9) Å. X-ray absorption near edge structure (XANES) and extended X-ray absorption fine structure (EXAFS) measurements suggest that the niobium is located in an octahedral coordination environment. Optical measurements inform us that the niobium dopant acts as the activator. The synthesis, structure, and optical properties are reported, including radioluminescence (RL) measurements under X-ray irradiation.
- Open Access
- 27 December 2021
- Published by American Chemical Society (ACS) in ACS Omega
- Vol. 7 (1) , 362-371
Correlational Approach to Predict the Enthalpy of Mixing for Chloride Melt Systems
A methodology to estimate the heat of mixing (ΔmixH) for salt liquids in unexplored AkCl–AnClx/LnClx (Ak = alkali, An = actinide, Ln = lanthanide) systems is developed. It improves upon previous empirical approaches by eliminating the need for arbitrarily choosing the required composition at maximum short-range ordering, the minimum ΔmixH prior to performing the estimation, which avoids the intrinsic ambiguity of that approach. This semiempirical method has computationally reproduced the behavior of NaCl–UCl3 and KCl–UCl3 systems, providing ΔmixH values that agree well with the reported measurements within a propagated two standard deviations (2σ). The capability of the approach is demonstrated in its application to the entirety of the AkCl–UCl3 and AkCl–PuCl3 systems, the results from which have facilitated the accurate thermodynamic modeling of these and other AkCl–AnCl3/LnCl3 systems. The resultant assessed Gibbs energy functions and models have been incorporated in the Molten Salt Thermal Properties Database–Thermochemical (MSTDB-TC).
- 27 December 2021
- Published by American Chemical Society (ACS) in ACS Omega
- Vol. 7 (1) , 362-371
Open AccessCorrelational Approach to Predict the Enthalpy of Mixing for Chloride Melt Systems
A methodology to estimate the heat of mixing (ΔmixH) for salt liquids in unexplored AkCl–AnClx/LnClx (Ak = alkali, An = actinide, Ln = lanthanide) systems is developed. It improves upon previous empirical approaches by eliminating the need for arbitrarily choosing the required composition at maximum short-range ordering, the minimum ΔmixH prior to performing the estimation, which avoids the intrinsic ambiguity of that approach. This semiempirical method has computationally reproduced the behavior of NaCl–UCl3 and KCl–UCl3 systems, providing ΔmixH values that agree well with the reported measurements within a propagated two standard deviations (2σ). The capability of the approach is demonstrated in its application to the entirety of the AkCl–UCl3 and AkCl–PuCl3 systems, the results from which have facilitated the accurate thermodynamic modeling of these and other AkCl–AnCl3/LnCl3 systems. The resultant assessed Gibbs energy functions and models have been incorporated in the Molten Salt Thermal Properties Database–Thermochemical (MSTDB-TC).
- Open Access
Developing Practical Models of Complex Salts for Molten Salt Reactors
Molten salt reactors (MSRs) utilize salts as coolant or as the fuel and coolant together with fissile isotopes dissolved in the salt. It is necessary to therefore understand the behavior of the salts to effectively design, operate, and regulate such reactors, and thus there is a need for thermodynamic models for the salt systems. Molten salts, however, are difficult to represent as they exhibit short-range order that is dependent on both composition and temperature. A widely useful approach is the modified quasichemical model in the quadruplet approximation that provides for consideration of first- and second-nearest-neighbor coordination and interactions. Its use in the CALPHAD approach to system modeling requires fitting parameters using standard thermodynamic data such as phase equilibria, heat capacity, and others. A shortcoming of the model is its inability to directly vary coordination numbers with composition or temperature. Another issue is the difficulty in fitting model parameters using regression methods without already having very good initial values. The proposed paper will discuss these issues and note some practical methods for the effective generation of useful models.
Open AccessDeveloping Practical Models of Complex Salts for Molten Salt Reactors
Molten salt reactors (MSRs) utilize salts as coolant or as the fuel and coolant together with fissile isotopes dissolved in the salt. It is necessary to therefore understand the behavior of the salts to effectively design, operate, and regulate such reactors, and thus there is a need for thermodynamic models for the salt systems. Molten salts, however, are difficult to represent as they exhibit short-range order that is dependent on both composition and temperature. A widely useful approach is the modified quasichemical model in the quadruplet approximation that provides for consideration of first- and second-nearest-neighbor coordination and interactions. Its use in the CALPHAD approach to system modeling requires fitting parameters using standard thermodynamic data such as phase equilibria, heat capacity, and others. A shortcoming of the model is its inability to directly vary coordination numbers with composition or temperature. Another issue is the difficulty in fitting model parameters using regression methods without already having very good initial values. The proposed paper will discuss these issues and note some practical methods for the effective generation of useful models.
- Open Access
- 3 June 2021
- Published by MDPI AG in Preprints.org
Developing Practical Models of Complex Salts for Molten Salt Reactors
Olten salt reactors (MSRs) utilize salts as coolant or as the fuel and coolant together with fissile isotopes dissolved in the salt. It is necessary to therefore understand the behavior of the salts to effectively design, operate, and regulate such reactors, and thus there is a need for thermodynamic models for the salt systems. Molten salts, however, are difficult to represent as they exhibit short range order that is dependent on both composition and temperature. A widely useful approach is the modified quasichemical model in the quadruplet approximation that provides for consideration of first and second nearest neighbor coordination and interactions. Its use in the CALPHAD ap-proach to system modeling requires fitting parameters using standard thermodynamic data such as phase equilibria, heat capacity, and others. Shortcoming of the model is its inability to directly vary coordination numbers with composition or temperature. Another issue is the difficulty in fitting model parameters using regression methods without already having very good initial values. The proposed paper will discuss these issues and note some practical methods for the effective genera-tion of useful models.
- 3 June 2021
- Published by MDPI AG in Preprints.org
Open AccessDeveloping Practical Models of Complex Salts for Molten Salt Reactors
Olten salt reactors (MSRs) utilize salts as coolant or as the fuel and coolant together with fissile isotopes dissolved in the salt. It is necessary to therefore understand the behavior of the salts to effectively design, operate, and regulate such reactors, and thus there is a need for thermodynamic models for the salt systems. Molten salts, however, are difficult to represent as they exhibit short range order that is dependent on both composition and temperature. A widely useful approach is the modified quasichemical model in the quadruplet approximation that provides for consideration of first and second nearest neighbor coordination and interactions. Its use in the CALPHAD ap-proach to system modeling requires fitting parameters using standard thermodynamic data such as phase equilibria, heat capacity, and others. Shortcoming of the model is its inability to directly vary coordination numbers with composition or temperature. Another issue is the difficulty in fitting model parameters using regression methods without already having very good initial values. The proposed paper will discuss these issues and note some practical methods for the effective genera-tion of useful models.