AGR-1 post irradiation examination final report

PA Demkowicz - 2015 - osti.gov
The post-irradiation examination (PIE) of the Advanced Gas Reactor (AGR)-1 experiment
was a multi-year, collaborative effort between Idaho National Laboratory (INL) and Oak …

Silver (Ag) transport mechanisms in TRISO coated particles: A critical review

IJ Van Rooyen, ML Dunzik-Gougar… - Nuclear Engineering and …, 2014 - Elsevier
Transport of 110m Ag in the intact SiC layer of TRISO coated particles has been studied for
approximately 30 years without arriving at a satisfactory explanation of the transport …

Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel

PA Demkowicz, JD Hunn, DA Petti, RN Morris - Nuclear Engineering and …, 2018 - Elsevier
The AGR-1 irradiation experiment was performed as the first test of tristructural isotropic
(TRISO) fuel in the US Advanced Gas Reactor Fuel Development and Qualification Program …

Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test

JD Hunn, CA Baldwin, FC Montgomery… - … Engineering and Design, 2018 - Elsevier
Post-irradiation examination was completed on two as-irradiated compacts from the US
Advanced Gas Reactor Fuel Development and Qualification Program's second irradiation …

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 …

Irradiation performance of AGR-1 high temperature reactor fuel

PA Demkowicz, JD Hunn, SA Ploger, RN Morris… - … Engineering and Design, 2016 - Elsevier
The AGR-1 experiment contained 72 low-enriched uranium oxide/uranium carbide TRISO
coated particle fuel compacts in six capsules irradiated to burnups of 11.2 to 19.6% FIMA …

Identification of silver and palladium in irradiated TRISO coated particles of the AGR-1 experiment

IJ Van Rooyen, TM Lillo, YQ Wu - Journal of Nuclear Materials, 2014 - Elsevier
Evidence of the release of certain metallic fission products through intact tristructural
isotropic (TRISO) particles has been seen for decades around the world, as well as in the …

Production and characterization of TRISO fuel particles with multilayered SiC

RL Seibert, BC Jolly, M Balooch, DP Schappel… - Journal of Nuclear …, 2019 - Elsevier
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 …

Interaction of Stacking Faults with point/extended defects in Fe-He irradiated 6H-SiC

HS Sen, N Daghbouj, BS Li, AT AlMotasem, FF Ge… - Acta Materialia, 2023 - Elsevier
The study explored the microstructure evolution of 6H-SiC that underwent sequential iron
and helium ion irradiation with energies of 2.5 MeV and 500 keV, respectively, at room …

Thermal properties measurement of TRISO particle coatings from room temperature to 900° C using laser-based thermoreflectance methods

Y Wang, Z Hua, R Schley, G Beausoleil II… - Journal of Nuclear …, 2022 - Elsevier
The thermal properties of tristructural isotropic (TRISO) particle coatings have been
measured using laser-based thermoreflectance methods from room temperature to 900° C …