Correlational Approach to Predict the Enthalpy of Mixing for Chloride Melt Systems
Not Available
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
Engineering topics
Besmann, Theodore M.
Publications and source records attributed to Besmann, Theodore M..
FY21 Status Report on the Molten Salt Thermal Properties Database (MSTDB) Development
This report describes the thermodynamic assessments for the ZrF 4 -BeF 2 , AlCl 3 -NaCl, AlCl3-KCl and the PuCl 3 -CsCl pseudo-binary subsystems. Calculation results are compared to the inputs used to optimize the adjustable model parameters. The data came from experimental studies reported in the open literature, from the MSR research community, and/or computational results generated within the NEAMS program and from collaborators. The models from the thermodynamic assessment of these salt systems are integrated into the MSTDB-TC (Molten Salt Thermal Properties Database-Thermochemical). A brief description of the companion MSTDB-TP (Molten Salt Thermal Properties Database-Thermophysical) is given along with an overview of the approach for predicting both thermodynamic and thermophysical property behavior of multicomponent systems.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Separate-Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO 2 Pellets
We report a variety of normal operation and accident scenarios can generate thermal stresses large enough to cause cracking in light-water reactor (LWR) fuel pellets. Cracking of fuel pellets can lead to reduced heat removal, higher centerline temperatures, and localized stress in cladding, all of which impact fuel performance. It is important to experimentally characterize the thermal and mechanical behavior in the pellet before and after cracking to improve cracking models in fuel performance codes. However, in-reactor observation and measurement of cracking is very challenging due to the harsh environment and logistics. Recently, an experimental pellet cracking test stand was developed for separate effects testing of normal operations and accident temperature conditions, using thermal imaging to capture the pellet surface temperature for evaluation of thermal stresses and optical imaging to capture the evolution of cracking in real time. Experiments were performed using depleted uranium dioxide (UO 2 ) pellets, which are useful for collecting data valuable for development and validation of cracking models. A combination of induction and resistance heating was used to create an average temperature gradient of 236°C/cm and 193°C/cm before and after cracking respectively. Characterization of the pellets were done before as well as after cracking. The cracking patterns are somewhat different than those expected in a typical reactor because of the differences in thermal conditions and pellet microstructure. However, if the actual conditions of these experiments are reproduced in computational models, these out-of-pile tests on UO 2 pellets provide relevant data for modeling purposes.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products
A new formulation for redistribution of constituents in metallic U-Pu-Zr nuclear fuel is presented that can incorporate the contributions from fission products. The formulation is based on the thermodynamic driving forces derived from the generalized chemical potential that includes effects of composition and temperature. As a result, the redistribution model can readily account for the composition changes due to the generation of fission products while using only a limited set of transport coefficients. The thermodynamic model for the metallic fuel and thermochemistry solver Thermochimica were coupled with the nuclear fuel performance code BISON to implement the redistribution model. The simulations reproduce an experimentally observed Zr-depletion zone in the mid-radius region of an irradiated fuel slug. The generation of fission products during burnup is shown to have a stabilizing effect on the fuel chemistry, slowing the rate of U-Zr interdiffusion and reducing the size of the Zr-depleted zone. Here, the overall objective of the work is to advance predictive capabilities of fission product behaviour in U-Zr metallic fuel in the context of fuel performance and safety.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Interplay between London Dispersion, Hubbard U , and Metastable States for Uranium Compounds
High-throughput computational studies of lanthanide and actinide chemistry with density-functional theory are complicated by the need for Hubbard U corrections, which ensure localization of the f-electrons, but can lead to metastable states. This work presents a systematic investigation of the effects of both Hubbard U value and metastable states on the predicted structural and thermodynamic properties of four uranium compounds central to the field of nuclear fuels: UC, UN, UO 2 , and UCl 3 . We also assess the impact of the exchange-hole dipole moment (XDM) dispersion correction on the computed properties. Overall, the choice of Hubbard U value and inclusion of a dispersion correction cause larger variations in the computed geometric properties than result from metastable states. Further, the weak dependence of structure optimization on metastable states should simplify future high-throughput calculations on actinides. Conversely, addition of the dispersion correction is found to offset the repulsion introduced by the Hubbard U term and provides greatly improved agreement with experiment for both cell volumes and heats of formation. The XDM dispersion correction is largely invariant to the chosen U value, making it a robust dispersion correction for actinide systems.
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
Roadmap for thermal property measurements of Molten Salt Reactor systems
Thermal properties of molten salts, both with and without fissile and fertile material, are fundamental to modeling and simulation that supports design, construction, operation, and accident progression evaluation of molten salt reactors. This roadmap provides guidance to the research community on the types and amounts of required data for base, or carrier, salt systems, recommends simulated burnup fuel salt compositions to evaluate, and provides a technical foundation for a focused salt property evaluation matrix. The property values generated from both computation and experimental methods are used to develop models that constitute the Molten Salt Thermal Properties Database (MSTDB). While the building blocks of MSTDB are fundamental in nature, its data facilitates constructing engineering models that allow stakeholders to investigate the behavior of specific compositions of interest and supports broader modeling and simulation of MSRs through coupling to multi-physics, multi-scale mass accountancy tools.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Dimensional reduction upon calcium incorporation in Cs 0.3 (Ca 0.3 Ln 0.7 )PS 4 and Cs 0.5 (Ca 0.5 Ln 0.5 )PS 4
A series of Ca-containing lanthanide thiophosphates has been obtained and their structural evolution from 3D for LnPS 4 and Cs 0.3 (Ln 0.7 Ca 0.3 )PS 4 to 2D in Cs 0.5 (Ln 0.5 Ca 0.5 )PS 4 was shown as a function of Ca content. The first series with an idealized formula of Cs 0.3 (Ca 0.3 Ln 0.7 )PS 4 crystallizes in the R3¯m with combining macron]m space group and belongs to a new structure type that consists of a channel containing [(Ca 0.3 Ln 0.7 )PS 4 ] 0.3– framework, where the channels are occupied by severely disordered Cs + cations. A second new series with formula Cs 0.5 (Ca 0.5 Ln 0.5 )PS 4 crystallizes in the monoclinic C2/c space group and exhibits a layered structure consisting of [(Ca 0.5 Ln 0.5 )PS 4 ] 0.5– layers with Cs + cations located between the layers for charge balance. Together with the parent structure type, LnPS 4 , these three structure types illustrate how the LnPS 4 structure changes with Cs + cation incorporation, reducing its dimensionality from 3D to 2D. The magnetic properties of Cs 0.3 [(Ca 0.3 Ce 0.7 )PS 4 ] and Cs 0.3 [(Ca 0.3 Pr 0.7 )PS 4 ] were studied and revealed no magnetic transition down to 2 K.
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
Phase stability of U5Si4, USi, and U2Si3 in the uranium–silicon system
Not Available
Ulrich, Tashiema L.↗