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C is rhombohedral graphite-like structured and crystallizes in the hexagonal P6/mmm space group. The structure is two-dimensional and consists of one C sheet oriented in the (0, 0, 1) direction. C is bonded in a trigonal planar geometry to three equivalent C atoms. All C–C bond lengths are 1.42 Å.
C is Graphite-like structured and crystallizes in the monoclinic C2/m space group. The structure is two-dimensional and consists of one C sheet oriented in the (0, 0, 1) direction. C is bonded in a trigonal planar geometry to three equivalent C atoms. There is one shorter (1.42 Å) and two longer (1.43 Å) C–C bond length.
CuNH3Cl is Graphite-like structured and crystallizes in the cubic I2_13 space group. The structure is zero-dimensional and consists of eight CuNH3Cl clusters. Cu1+ is bonded in a linear geometry to one N3- and one Cl1- atom. The Cu–N bond length is 1.91 Å. The Cu–Cl bond length is 2.12 Å. N3- is bonded in a distorted tetrahedral geometry to one Cu1+ and three equivalent H1+ atoms. All N–H bond lengths are 1.03 Å. H1+ is bonded in a single-bond geometry to one N3- atom. Cl1- is bonded in a single-bond geometry to one Cu1+ atom.
C is rhombohedral graphite-like structured and crystallizes in the hexagonal P6/mmm space group. The structure is two-dimensional and consists of one C sheet oriented in the (0, 0, 1) direction. C is bonded in a trigonal planar geometry to three equivalent C atoms. All C–C bond lengths are 1.43 Å.
GeSn is graphite-derived structured and crystallizes in the trigonal P3m1 space group. The structure is two-dimensional and consists of one GeSn sheet oriented in the (0, 0, 1) direction. Sn is bonded in a trigonal non-coplanar geometry to three equivalent Ge atoms. All Sn–Ge bond lengths are 2.63 Å. Ge is bonded in a trigonal non-coplanar geometry to three equivalent Sn atoms.
C is rhombohedral graphite-like structured and crystallizes in the hexagonal P6_3/mmc space group. The structure is two-dimensional and consists of two C sheets oriented in the (0, 0, 1) direction. C is bonded in a trigonal planar geometry to three equivalent C atoms. All C–C bond lengths are 1.42 Å.
N2 is graphite-like structured and crystallizes in the cubic I2_13 space group. The structure is three-dimensional. N is bonded in a trigonal non-coplanar geometry to three equivalent N atoms. All N–N bond lengths are 1.41 Å.
C is rhombohedral graphite-like structured and crystallizes in the cubic I4_132 space group. The structure is three-dimensional. C is bonded in a trigonal planar geometry to three equivalent C atoms. All C–C bond lengths are 1.46 Å.
C is rhombohedral graphite-like structured and crystallizes in the hexagonal P6/mmm space group. The structure is two-dimensional and consists of one C sheet oriented in the (0, 0, 1) direction. C is bonded in a trigonal planar geometry to three equivalent C atoms. All C–C bond lengths are 1.42 Å.
CuS is graphite-derived structured and crystallizes in the trigonal P3m1 space group. The structure is two-dimensional and consists of one CuS sheet oriented in the (0, 0, 1) direction. Cu2+ is bonded in a trigonal non-coplanar geometry to three equivalent S2- atoms. All Cu–S bond lengths are 2.15 Å. S2- is bonded in a trigonal non-coplanar geometry to three equivalent Cu2+ atoms.
Graphite anisotropic microstructure Graphite crystal structure and basal planes Response to irradiation and temperature C-axis and a-axis behavior The effect of porosity Nano-and micro-length scale Microscopic to macroscopic response Material property changes Defect length-scale factors Internal stress build-up Irradiation induced dimensional change Temperature effects Stress increases & property changes
A nuclear reactor is disclosed including a reactor core and a reflector assembly surrounding the reactor core. The reflector assembly includes a stationary reflector component including a graphite support structure comprising a plurality of channels defined therein and a plurality of beryllium-oxide pins positioned in the channels.
The DOE neams program supports a full range of computational thermal fluids analysis capabilities and code developments for a broad range of advanced reactor concepts. The research and development approach under the thermal fluids technical area synergistically combines three length and time scales in a hierarchical multi-scale approach. To enable multi-scale thermal fluids capability using these codes, a key joint effort has been underway to develop an integrated system- and engineering-scale thermal fluids analysis capability, through integration of SAM and Pronghorn codes, both based on the MOOSE framework. This report summarizes recent advances in developing an integrated system- and engineering-scale modeling capability for the msr concept, which has gained significant interest in recent years. A consistent framework was established by coupling Pronghorn and SAM through the Saline interface, with thermophysical properties provided by the Molten Salt Thermal Property Database (MSTDB-TP). Further improvements were made to the coupling schemes and domain-overlapping strategies, enhancing the stability and robustness of multi-code simulations. Verification and validation efforts demonstrate the accuracy of this integration across a range of benchmark problems, including one-dimensional heated pipe flows, three-dimensional natural convection loops with evolving isotopic compositions, and \gls{msre} demonstration cases. Within Pronghorn, new capabilities were introduced to model corrosion and noble-metal plating phenomena, supported by an extended thermal-hydraulics framework and refined turbulence treatments. To capture two-phase flow behavior, a multiphase Euler–Euler model was implemented in Pronghorn, including advanced closure relations, high-resolution advection techniques, and capillary force reconstruction. Preliminary verification cases confirm the fidelity of the approach, while planned validation efforts target canonical multiphase benchmarks and application to msr components such as the msre pump bowl. Finally, updates to SAM’s msr mass transfer modeling were extended to consider noble gas migration into porous structures like graphite. The point kinetics model was updated to include reactivity feedback contributions from any defined species, such as xenon. The gas transport model was expanded for applicability to gas mixtures, bubble efflux phenomena, and species transport between liquid and gas phases. A selection of multi-scale Sherwood number correlations from MOSCATO/NekRS and multi-phase correlations from literature have been added for improved accuracy in calculating mass transfer coefficients. A companion effort on developing system-level redox corrosion has also been incorporated into SAM. Collectively, these enhancements strengthen the predictive capability of SAM and Pronghorn for simulating MSR thermal-hydraulics, corrosion, multiphase behavior, and fission-product transport, providing a more complete toolset for design, safety analysis, and licensing support of next-generation \gls{msr}s.
The document reports on the design, construction, testing and initial operation of the ORNL graphite intrusion system with pressurized molten salts. This technical memorandum is responsive to work package AT-20OR04060203, “Graphite-Salt Studies” —ORNL”, and fulfills Milestone M3AT20OR040602035 “Report on graphite-salt intrusion studies”.The report outlines the procedure of graphite intrusion experiments, which follows the ASTM standard guidance, and the procedures of other characterization measurements of graphite physical properties, also based on ASTM standard methods. A set of 12 graphite grades of various origin and properties went through preliminary characterizations, and six of them were further selected for intrusion experiments with molten FLiNaK. The results are discussed in the context of graphite physical properties and are compared with a several results from literature. The correlation between molten salt impregnation and mercury intrusion, first proposed by MSRE scientists, is discussed in detail. Pending collection of more data, the mercury intrusion porosimetry technique may possibly be used as a rapid method for screening and down selection of graphite grades with extremely low salt intrusion, as required for operation in molten salt reactors. This new system will generate data non only on intrusion behavior, but will also generate a wide range of salt- impregnated graphite samples that will be further analyzed with advanced characterization techniques for better understanding of the effect of salt intrusion on the properties of nuclear graphite. It expected that these results and future results obtained with this system will help advance our understanding of the factors controlling the extent of salt penetration in graphite and of the relationship with intrinsic structural properties of various grades. Together, correlating direct measurements results and graphite structural properties should allow development of a predictable model that could be used for selection and qualification of optimal graphite grades, tailored to design operation conditions and molten salt properties.
Structure of the program Graphite material issues of interest How do things fit together Status of the program Baseline AGC Experiment Update AGC-4 and HDG-1 Irradiation Oxidation Modeling ASME Code development Discussion of how the data can be used Modeling behavior of core components Licensing/code development Interaction with vendors Collaborations (domestic and international)
Here, we have studied the high-pressure vibrational and structural behavior of bulk graphite and graphene nanoplatelets at room temperature by means of high-pressure Raman spectroscopic and x-ray diffraction probes. We have detected a clear pressure-induced structural transition in both materials, evidenced by the appearance of new Bragg peaks and Raman features, deviating from the starting hexagonal graphitic structure. The high-pressure phase is identified as a partially disordered orthorhombic structure, consisting of mixed sp 2 - and sp 3 -type bonding. Our experimental findings serve as direct evidence for the existence of a metastable transient modification in cold compressed carbon, lying between the sp 2 -type graphite and sp 3 -type diamond allotropes.
Intrinsic structural and oxidic defects activate graphitic carbon electrodes towards electrochemical reactions underpinning energy conversion and storage technologies. Yet, these defects can also disrupt the long-range and periodic arrangement of carbon atoms, thus, the characterization of graphitic carbon electrodes necessitates in-situ atomistic differentiation of graphitic regions from mesoscopic bulk disorder. Here, we leverage the combined techniques of in-situ attenuated total reflectance infrared spectroscopy and first-principles calculations to reveal that graphitic carbon electrodes exhibit electric-field dependent infrared activity that is sensitive to the bulk mesoscopic intrinsic disorder. With this platform, we identify graphitic regions from amorphous domains by discovering that they demonstrate opposing electric-field-dependent infrared activity under electrochemical conditions. Our work provides a roadmap for identifying mesoscopic disorder in bulk carbon materials under potential bias.
Irradiation-induced defect evolution in graphite is particularly important for its application in graphite-moderated nuclear reactors. The evolution of defects directly influences macroscopically observed property changes in irradiated nuclear graphite which, in turn, can govern the lifetime of graphite components. This article reports novel defect structures and the irradiation response of microstructural features occurring in high-temperature irradiated nuclear graphite IG-110. High resolution transmission electron microscopy (HRTEM) was used to characterize specimens neutron-irradiated at a high temperature (≥ 800°C) at doses of 1.73 and 3.56 atomic displacements per atom (dpa). Concentric shelled and fullerene-like defects were found to result in swelling along the c-axis and contraction along the a/b-axis of crystallites. Furthermore, such defects are shown to occur within, and partially fill, Mrozowski cracks prior to turnaround dose. In addition, in situ TEM under similar irradiation conditions was used to capture the real-time dynamic evolution of defects, providing unambiguous analysis of the evolution of the graphite structures during irradiation. Here, the results suggest the mainstream theory for radiation damage in nuclear graphite (which assumes additional basal plane formation as the sole reason) to be an incorrect interpretation of defect evolution contributing to irradiation-induced property changes at higher temperatures.