Effect of H and Pd atoms on the migration of He atoms in 3C–SiC

S Zhao, C Chen, G Ran - Progress in Nuclear Energy, 2023 - Elsevier
Abstract 3C–SiC is an important structural material for tri-structural isotropic coated fuel
particles in high-temperature gas reactors. It serves as a vital pressure vessel for gas fission …

AGR-2 TRISO fuel post-irradiation examination final report

JD Stempien, RN Morris, TJ Gerczak, PA Demkowicz - 2021 - osti.gov
An array of post-irradiation exams and experiments were employed to assess the irradiation
performance and high-temperature behavior of AGR-2 UCO TRISO fuel produced in an …

Comparison of microstructural and micro-chemical evolutions in the irradiated fuel kernels of AGR-1 and AGR-2 TRISO fuel particles

Z Fu, L He, IJ van Rooyen, Y Yang - Progress in Nuclear Energy, 2024 - Elsevier
The US Advanced Gas Reactor (AGR) tristructural isotropic (TRISO) fuel represents the
culmination of significant development efforts aimed at overcoming limitations observed in …

Anisotropic temperature-dependent elastic constants and thermal conductivities of TRISO particle coatings

JA Evans, RA Lebensohn, JR Harter… - Journal of Nuclear …, 2022 - Elsevier
Tristructural isotropic (TRISO) particles show great promise as a candidate fuel for use in
several next-generation high-temperature nuclear reactor designs due to their structural …

Investigation of the structure and chemical nature of Pd fission product agglomerations in irradiated TRISO particle SiC

EJ Olivier, JH Neethling, IJ Van Rooyen - Journal of Nuclear Materials, 2020 - Elsevier
Abstract Tristructural-isotropic (TRISO)-coated fuel particles are used in high-temperature
gas-cooled nuclear reactors. Although the polycrystalline 3C–SiC layer acts as the main …

Role of microstructure on CO corrosion of SiC layer in UO2-TRISO fuel

TJ Gerczak, R Seibert, JD Hunn - Journal of Nuclear Materials, 2020 - Elsevier
Abstract The Advanced Gas Reactor Fuel Qualification and Development (AGR) program
has focused on qualification of UCO kernel tristructural-isotropic (TRISO) particle fuel …

Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800° C safety testing

TJ Gerczak, RL Seibert, JD Hunn, CA Baldwin… - Journal of Nuclear …, 2020 - Elsevier
Release of radionuclides from intact tristructural-isotropic (TRISO) coated particle fuel at
normal and accident conditions is a primary metric of fuel performance. The distribution of …

Understanding of fission products transport in SiC layer of TRISO fuels by nanoscale characterization and modeling

S Meher, IJ van Rooyen, C Jiang - Journal of Nuclear Materials, 2019 - Elsevier
This paper details recent advances in the understanding of both intergranular and
intragranular fission product transport in the silicon carbide (SiC) layer of neutron-irradiated …

Microstructure and fission products in the UCO kernel of an AGR-1 TRISO fuel particle after post irradiation safety testing

Z Fu, IJ van Rooyen, M Bachhav, Y Yang - Journal of Nuclear Materials, 2020 - Elsevier
Tristructural isotropic (TRISO) coated particle fuel, as a key fuel concept for the high-
temperature gas-cooled reactors and a candidate accident-tolerant fuel, has been …

Ab initio study and thermodynamic modeling of the Pd-Si-C system

C Jiang, IJ van Rooyen, S Meher - Computational Materials Science, 2020 - Elsevier
Understanding phase stability in the Pd-Si-C ternary system is important for predicting the
high-temperature behavior of tristructural isotropic (TRISO) nuclear fuels for high …