A study of fission product migration paths in irradiated TRISO particle SiC
Tristructural isotropic (TRISO) coated fuel particles used in high-temperature gas-cooled nuclear reactors (HTGRs) provide key advantages in terms of passive safety and reactor energy efficiencies. TRISO fuel consists of a number of special coating layers surrounding the fissile material in the kernel as shown in Fig. 1. The coating layers consist of a carbon buffer layer, inner pyrolytic carbon (PyC) layer, a silicon carbide (SiC) layer as well as an outer pyrolytic carbon layer. Together the layers act as a pressure vessel and barrier to the release of radioactive fission products into the reactor environment. The cubic 3C-SiC layer of thickness approximately 35 µm, acts as the primary barrier to the migration of metallic fission products out of the particle. The finding, more than three decades years ago, that silver can be released by intact TRISO particles has led to significant research to determine possible transport mechanisms of certain fission products in SiC. Out-of-reactor experiments did not reveal any significant lattice diffusion of silver in SiC1. Many earlier findings alternatively proposed a dominating role of fast diffusion paths such as grain boundaries and dislocations in enhancing fission product migration in SiC. Recently the role of the fission product palladium in enhancing the transport rate of silver in SiC2 was confirmed by transmission electron microscopy (TEM) of neutron-irradiated SiC from a TRISO coated particle from Compact 4-1-1, which was irradiated to an average burnup of 19.38% fissions per initial metal atom (FIMA); a time-averaged, volume-averaged temperature of 1072 °C; a time-averaged peak temperature of 1182 °C; and an average fast fluence of 4.13 x 1021 n/cm2 as part of the US Department of Energy's Advanced Gas Reactor (AGR)-1 experiment3. Although other studies found that Ag was found separately (without Pd) in TRISO coated particles irradiated at 11.4 %, 16.7 and 18.6% FIMA, Pd could have been present at lower than measureable concentrations4. In this study, SiC focussed ion beam (FIB) sections obtained from Compact 4-1-1 from the AGR-1 experiment were analysed in a double Cs-corrected JEOL ARM 200F using atomically resolved scanning transmission electron microscopy (STEM). By using atom resolved STEM in combination with electron energy loss spectroscopy (EELS) and large angle energy dispersive spectroscopy (EDS) a much better understanding of the migration routes and mechanisms of fission products in irradiated polycrystalline 3C-SiC was achieved.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- C020
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1556077
- Report Number(s):
- INL-CON-18-50121-Rev000
- Resource Relation:
- Conference: 19th International Microscopy Congress (IMC19), Sydney Australia, 09/09/2018 - 09/14/2018
- Country of Publication:
- United States
- Language:
- English
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