Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles (HTR2018)
Abstract
Abstract – Metallic fission products are found to transport through the SiC layer of the tristructural isotropic (TRISO) fuel particle and various studies has been undertaken to understand the transport behavior. It has been recently discovered that the precipitation of intragranular palladium containing fission products in SiC layer of neutron-irradiated TRISO fuel particles occurs via a novel dual-step nucleation mechanism. Direct observations of Pd silicide imprinting into morphological templates of a-SiC precipitates in neutron irradiated SiC layer of TRISO fuel will be discussed with examples from selected particles from both the Advanced Gas Reactor (AGR)-1 (fabricated laboratory-scale at Oak Ridge National Laboratory) and AGR-2 (fabricated at pilot scale by an industrial vendor) experiments. As neutron irradiation damage structures are expected to accelerate the intragranular diffusion kinetics of fission products, their size, shape, density and distribution patterns across the radial thickness of the SiC layer can be directly correlated with the nature of intragranular transport pathways of fission products. In this work, the distinction of neutron irradiation damage structures as a function of fuel type, burnup level and fabrication histories of TRISO coated particles from the AGR-1 and AGR-2 experiments has been studied. The five particles investigated, three AGR-1 and twomore »
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1478815
- Report Number(s):
- INL/CON-18-45560-Rev000
- DOE Contract Number:
- AC07-05ID14517
- Resource Type:
- Conference
- Resource Relation:
- Conference: HTR2018, Warsaw Poland, 10/08/2018 - 05/10/2018
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; TRISO; Advanced Gas Reactor (AGR); Very High Temperature Gas Cool Reactor (VHTR)
Citation Formats
Rooyen, I.J. van, Meher, S., and Rosales, J. Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles (HTR2018). United States: N. p., 2018.
Web.
Rooyen, I.J. van, Meher, S., & Rosales, J. Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles (HTR2018). United States.
Rooyen, I.J. van, Meher, S., and Rosales, J. Mon .
"Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles (HTR2018)". United States. https://www.osti.gov/servlets/purl/1478815.
@article{osti_1478815,
title = {Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles (HTR2018)},
author = {Rooyen, I.J. van and Meher, S. and Rosales, J.},
abstractNote = {Abstract – Metallic fission products are found to transport through the SiC layer of the tristructural isotropic (TRISO) fuel particle and various studies has been undertaken to understand the transport behavior. It has been recently discovered that the precipitation of intragranular palladium containing fission products in SiC layer of neutron-irradiated TRISO fuel particles occurs via a novel dual-step nucleation mechanism. Direct observations of Pd silicide imprinting into morphological templates of a-SiC precipitates in neutron irradiated SiC layer of TRISO fuel will be discussed with examples from selected particles from both the Advanced Gas Reactor (AGR)-1 (fabricated laboratory-scale at Oak Ridge National Laboratory) and AGR-2 (fabricated at pilot scale by an industrial vendor) experiments. As neutron irradiation damage structures are expected to accelerate the intragranular diffusion kinetics of fission products, their size, shape, density and distribution patterns across the radial thickness of the SiC layer can be directly correlated with the nature of intragranular transport pathways of fission products. In this work, the distinction of neutron irradiation damage structures as a function of fuel type, burnup level and fabrication histories of TRISO coated particles from the AGR-1 and AGR-2 experiments has been studied. The five particles investigated, three AGR-1 and two AGR-2 particles, represent irradiation histories of four fuel types with burnup levels varying from 12.55 to 17.4 % fissions per initial metal atom.},
doi = {},
url = {https://www.osti.gov/biblio/1478815},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {10}
}