journal article·2019-03Open access

Production and characterization of TRISO fuel particles with multilayered SiC

Rachel L. Seibert, Brian C. Jolly, Mehdi Balooch, Daniel P. Schappel, Kurt A. Terrani

Abstract

Abstract Three distinct composite architectures of silicon carbide (SiC) and pyrocarbon (PyC) were incorporated into the SiC coating layer of tristructural-isotropic (TRISO) nuclear fuel particles. The composite architectures are meant to increase the resistance of SiC coating layer to cracking and fission product attack during operation and accident scenarios. All composite layers were produced using the existing fluidized bed chemical vapor deposition apparatus that is used for production of TRISO fuel particles without modifications. Detailed characterization of the composite microstructure was carried out via optical and electron microscopy. Nano-indentation examination confirms that mechanical properties of the SiC phase was not affected in the composite architectures, however, the resistance to crack propagation in this coating layer was greatly increased in all cases when compared to the reference monolithic coating layer. The stress required to debond the SiC-inner PyC interface in the reference TRISO particles was determined to be ∼1 GPa using micropillar compression technique. The high strength may explain the ease of crack propagation from the inner PyC to SiC in the reference design. In the composite architectures, the means of crack deflection were effectively incorporated at this interface. Finite element analysis of stress evolution in the fuel particles during normal operation with the reference and composite SiC coating layer architectures did not show any significant differences between the variants.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (59)

Show source-provided references
1. Daniels · 1944
2. McCullough · 1947
3. The early history of high-temperature helium gas-cooled nuclear power reactors10.1016/0360-5442(91)90084-Y ↗
4. Hanson · 2004
5. 2010
6. Miller · 2009
7. Development of improved models and designs for coated-particle gas reactor fuels
8. Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance10.1016/S0029-5493(03)00033-5 ↗
9. Hunn · 2006
10. Irradiation performance of AGR-1 high temperature reactor fuel10.1016/j.nucengdes.2015.09.011 ↗
11. Microencapsulated fuel technology for commercial light water and advanced reactor application10.1016/j.jnucmat.2012.05.021 ↗
12. Uranium kernel formation via internal gelation10.1524/ract.92.12.909.55110 ↗
13. Long time experience with the development of HTR fuel elements in Germany10.1016/S0029-5493(02)00128-0 ↗
14. Production of spherical UO2-UC2 for nuclear fuel applications using thermochemical principles10.1111/j.1151-2916.1982.tb10463.x ↗
15. Preparation of uranium nitride in the form of microspheres10.1016/0022-3115(92)90450-Y ↗
16. Quantification of process variables for carbothermic synthesis of UC 1-x N x fuel microspheres10.1016/j.jnucmat.2016.11.006 ↗
17. TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTS) for fission product transport Ddue to manufacturing
18. Demkowicz · 2015
19. Lowden · 2006
20. Kercher · 2005
21. Chemical vapor deposition in fluidized bed reactors10.1016/0257-8972(92)90165-7 ↗
22. Jolly · 2015
23. Barnes · 2006 · vol. 8
24. Jolly · 2016
25. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments10.1557/JMR.1992.1564 ↗
26. Materials properties of a sintered alpha-SiC10.1063/1.556000 ↗
27. Handbook of SiC properties for fuel performance modeling10.1016/j.jnucmat.2007.05.016 ↗
28. Determination of interfacial mechanical properties of ceramic composites by the compression of micro-pillar test specimens10.1007/s10853-013-7311-z ↗
29. On the Coulomb-Mohr failure criterion 196910.1029/JB074i022p05343 ↗
30. Micro-mechanical evaluation of SiC-SiC composite interphase properties and debond mechanisms10.1016/j.compositesb.2017.07.035 ↗
31. Multidimensional multiphysics simulation of nuclear fuel behavior10.1016/j.jnucmat.2012.01.012 ↗
32. Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation
33. Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON10.1016/j.nucengdes.2018.05.018 ↗
34. Verfondern · 2012
35. 2012
36. Mechanical characteristics of SiC coating layer in TRISO fuel particles10.1016/j.jnucmat.2013.08.041 ↗
37. Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: properties and irradiation effects10.1016/j.jnucmat.2013.06.040 ↗
38. Hardness and elastic modulus of amorphous and nanocrystalline SiC and Si films10.1016/j.surfcoat.2007.07.029 ↗
39. Ortec Advanced Ceramics, CVD Silicon Carbide (SiC) – Properties & applications, (n.d.). https://www.ortechceramics.com/creamic-materials/cvd-silicon-carbide-2/(accessed July 24, 2018).
40. Allen · 2012
41. Graves · 1994
42. Determining the shear properties of the PyC/SiC interface for a model TRISO fuel10.1016/j.jnucmat.2006.01.004 ↗
43. Young's modulus measurements of SiC coatings on spherical particles by using nanoindentation10.1016/j.jnucmat.2009.05.001 ↗
44. Effects of thermal treatment on the mechanical integrity of silicon carbide in HTR fuel up to 2200°C10.1016/j.jnucmat.2014.03.039 ↗
45. Detection and analysis of particles with failed SiC in AGR-1 fuel compacts10.1016/j.nucengdes.2015.12.011 ↗
46. Fracture toughness and flexural strength of chemically vapor-deposited silicon carbide as determined using chevron-notched and surface crack in flexure specimens10.1111/j.1551-2916.2004.01093.x ↗
47. Characterization of vickers, berkovich, spherical and cube cornered diamond indenters by nanoindentation and sfm
48. Hunn · 2013
49. Hunn · 2015
50. Microscopic analysis of irradiated AGR-1 coated particle fuel compacts10.1016/j.nucengdes.2013.11.036 ↗
51. Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test10.1016/j.nucengdes.2017.09.017 ↗
52. Identification of silver and palladium in irradiated TRISO coated particles of the AGR-1 experiment10.1016/j.jnucmat.2013.11.028 ↗
53. Electron microscopic evaluation and fission product identification of irradiated TRISO coated particles from the AGR-1 experiment: a preliminary review10.1016/j.nucengdes.2013.11.019 ↗
54. Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle10.1016/j.jeurceramsoc.2018.05.003 ↗
55. Local atomic structure of Pd and Ag in the SiC containment layer of TRISO fuel particles fissioned to 20% burn-up10.1016/j.jnucmat.2017.12.032 ↗
56. Demkowicz · 2017
57. Nuclear fuels – present and future10.1016/j.jnucmat.2009.01.297 ↗
58. NGNP Fuel Qualification White Paper, INL/EXT-10-18610, (n.d).
59. Fission product palladium-silicon carbide interaction in HTGR fuel particles10.1016/0022-3115(90)90264-N ↗