Densification and thermal properties of cylindrical graphite-based fuel elements used in a molten salt reactor
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Graphite, nuclear technology, radiation studies · Nuclear reactor physics and engineering · Heat transfer and supercritical fluids
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (47)
Show source-provided references
1. Effective gaseous diffusion coefficients of select ultra-fine, super-fine and medium grain nuclear graphite[J]10.1016/j.carbon.2018.05.003 ↗
2. Densification of matrix graphite for spherical fuel elements used in molten salt reactor via addition of green pitch coke[J]10.1016/j.net.2021.09.034 ↗
3. Mesocarbon microbead based graphite for spherical fuel element to inhibit the infiltration of liquid fluoride salt in molten salt reactor[J]10.1016/j.jnucmat.2017.04.003 ↗
4. Determining the oxidation behavior of matrix graphite[J]10.1016/j.jnucmat.2023.154849 ↗
5. Properties and microstructures of a matrix graphite for fuel elements of pebble-bed reactors after high-temperature purification at different temperatures[J]10.1016/S1872-5805(21)60048-3 ↗
6. Characterization and ion-irradiation studies of typical microstructures in nuclear graphite[J]10.1016/j.jnucmat.2023.154848 ↗
7. Advances in high temperature gas-cooled reactor technology developments and related IAEA activities to support near-term deployment[J]10.1063/5.0095967 ↗
8. Preparation of ultrafine-grain graphite by liquid dispersion technique for inhibiting the liquid fluoride salt infiltration[J]10.1016/j.carbon.2016.02.018 ↗
9. Characterization of the effects of 3-MeV proton irradiation on fine-grained isotropic nuclear graphite[J]10.1016/j.carbon.2014.05.034 ↗
10. Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors[J]10.1016/j.net.2020.10.018 ↗
11. Preparation of binderless nanopore-isotropic graphite for inhibiting the liquid fluoride salt and Xe135 penetration for molten salt nuclear reactor[J]10.1016/j.carbon.2014.07.022 ↗
12. Densification of A3-3 matrix graphite to inhibit the infiltration of liquid FLiBe salt in molten salt reactors[J]10.1016/j.mtcomm.2021.102242 ↗
13. Carbon black densified matrix graphite to enhance its anti-infiltration capability against molten salt[J]10.1016/j.carbon.2024.119844 ↗
14. Stability analysis on two single-phase coupled natural circulation loops[J]10.1016/j.ijheatmasstransfer.2024.125886 ↗
15. Conceptual design of a 3 MWth yttrium hydride moderated heat pipe cooled micro reactor[J]10.1016/j.nucengdes.2022.111931 ↗
16. Fuel depletion study of the molten salt demonstration reactor[J]10.1016/j.nucengdes.2023.112881 ↗
17. Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel[J]10.1016/j.anucene.2023.109974 ↗
18. Characterization of molten 2LiF–BeF2 salt impregnated into graphite matrix of fuel elements for thorium molten salt reactor[J]10.1007/s41365-019-0600-8 ↗
19. Liquid fuel molten salt reactors for thorium utilization[J]10.13182/NT15-124 ↗
20. Molten salt for advanced energy applications: A review[J]10.1016/j.anucene.2021.108924 ↗
21. Molten FLiNaK salt infiltration into degassed nuclear graphite under inert gas pressure[J]10.1016/j.carbon.2014.12.044 ↗
22. Effects of compositions of filler, binder and porosity on elastic and fracture properties of nuclear graphite[J]10.1016/j.jnucmat.2014.10.071 ↗
23. The infiltration behavior and chemical compatibility of molten lead-bismuth eutectic in nuclear graphite at elevated temperature[J]10.1016/j.jnucmat.2021.152921 ↗
24. ASTM C781-08, Standard practice for testing graphite and boronated graphite materials for high-temperature gas-cooled nuclear reactor components[P], 2008.
25. Numerical study of TRISO particles with random size and location distribution in cuboid and cylindrical matrix: A validation for two-regime heat conduction model[J]10.1016/j.nucengdes.2024.113193 ↗
26. Fabrication of matrix graphite with a high degree of graphitization for spherical fuel elements by using natural microcrystalline graphite fillers[J]10.1016/j.net.2024.06.049 ↗
27. Microstructural characterization and pore structure analysis of nuclear graphite[J]10.1016/j.jnucmat.2011.05.053 ↗
28. Effect of heating rate, temperature, and residence time during graphitization on the mechanical and electrical properties of isotropic graphite blocks[J]10.1016/j.carbon.2023.03.069 ↗
29. Improving molten fluoride salt and Xe135 barrier property of nuclear graphite by phenolic resin impregnation process[J]10.1016/j.jnucmat.2017.11.019 ↗
30. XRD graphitization degrees: A review of the published data and new calculations, correlations, and applications[J]10.52321/GeolBalc.50.1.11 ↗
31. Microstructural characterisation of nuclear grade graphite[J]10.1016/j.jnucmat.2008.07.038 ↗
32. Raman spectroscopic investigation of graphitization of diamond during spark plasma sintering of UO2-diamond composite nuclear fuel[J]10.1016/j.jnucmat.2016.03.015 ↗
33. Neutron irradiation damage of nuclear graphite studied by high-resolution transmission electron microscopy and Raman spectroscopy[J]10.1016/j.jnucmat.2015.10.027 ↗
34. Graphite behavior and its effects on MSBR performance[J]10.1016/0029-5493(69)90057-0 ↗
35. Anisotropy of coefficient of thermal expansion of nuclear graphite under compressive stresses[J]10.1016/j.nucengdes.2010.10.005 ↗
36. Measurement of contact angle in systems involving liquid metals[J]10.1088/0957-0233/7/5/005 ↗
37. Mercury porosimetry: A general (practical) overview[J]10.1002/ppsc.200601009 ↗
38. Sohal S M, Ebner A M, Sabharwall P, et al. Engineering database of liquid salt thermophysical and thermochemical properties[R]. INL/EXT-10-18297, 980801, 2010: INL/EXT-10-18297, 980801.
39. Encapsulation of high-temperature inorganic phase change materials using graphite as heat transfer enhancer[J]10.1016/j.renene.2018.09.107 ↗
40. Research on the molten salt infiltration characteristics and mechanical properties of nuclear graphite in the molten salt reactor environment[D]
41. Tang · 2007 · 43
42. Fully coupled multiphysics modeling of enhanced thermal conductivity UO2 –BeO fuel performance in a light water reactor[J]10.1016/j.nucengdes.2015.10.019 ↗
43. Manufacture and characteristics of spherical fuel elements for the HTR-10[J]10.1016/j.nucengdes.2005.10.023 ↗
44. Xu · 2017 · 68
45. Numerical study of tritium transport characteristics in thorium molten salt reactor with solid fuel (TMSR-SF)[J]10.1016/j.nucengdes.2018.06.013 ↗
46. Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet[J]
47. Fluoride salt coolant properties for nuclear reactor applications: A review[J]10.1016/j.anucene.2017.05.036 ↗