Comparison of AGR-3/4 Fission Product Transport Model to Measurements and Extraction of Diffusivities via Analytical Fits
A one-dimensional finite-element model based on the MOOSE framework has been constructed, and overall transport estimates are predicted based on available diffusivities and sorption isotherms in the extant literature. The predicted transport profiles are compared to experimental results, where such results are available, including total inventory analysis of gamma emitters, liquid scintillation results for Sr-90 […]
X-ray computed tomography of deconsolidated TRISO Particles from the AGR-5/6/7 irradiation experiment capsule 1 Compact
X-ray Computed Tomography (XCT) was performed on TRISO particles from fuel Compact 1-7-9 from Capsule 1 of the AGR-5/6/7 irradiation experiment. Compact 1–7–9 was in the vicinity of overheated thermocouples that released transition metals and caused significant damage and failure of TRISO particles within regions of Capsule 1. Four particles, Particles A–D, were non-destructively examined […]
Fission Product Distribution in Irradiated Safety-Tested and As-Irradiated AGR-2 TRISO Particles
Two tristructural isotropic (TRISO)-coated nuclear fuel particles were examined by electron probe microanalysis (EPMA) as part of the Advanced Gas Reactor program. The compacts’ average irradiation temperatures ranged from approximately 1260 to 1290 °C. One particle was examined in the as-irradiated condition, while the other was subject to 1600 °C post-irradiation safety testing. This study […]
AGR-3/4 Post-Irradiation Examination
Updates on AGR-3/4 PIE at INL and ORNL for the July 2021 review meeting with DOE sponsors.
Catalyzed oxidation of IG-110 nuclear graphite by simulated fission products Ag and Pd nanoparticles
To evaluate the stability of nuclear materials in high temperature gas reactors under air ingress conditions, catalytic oxidation of IG-110 graphite by two simulated fission products, metallic Pd and Ag, was studied in oxidative atmosphere and at temperatures up to 1000ºC using an integrated furnace, mass spectroscopy and infrared spectroscopy system. Transmission electron microscopy and […]
AGR TRISO Fuel Fission Product Release Data Summary
Knowledge of fission product retention in and release from TRISO fuel under normal and off-normal conditions is needed for reactor safety analyses. This is important for coated-particle fuel used in high-temperature reactors relying on the functional containment strategy. Data on the release and retention of key fission products (e.g., Ag-110m, Cs-134, Eu-154, and Sr-90) in […]
AGR-5/6/7 Irradiation Disassembly and Metrology First Look
The AGR-5/6/7 irradiation test train was sectioned at ATR and sent to HFEF for examination and disassembly. Visual examinations of the test train exterior did not indicate any notable damage or degradation. Prior to disassembly, the two test train sections were subjected to analysis via gamma scanning and neutron radiography, and those non-destructive exams did […]
Catalyzed oxidation of nuclear graphite by simulated fission products Sr, Eu, and I
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite was studied in the temperature range of 400 to 1000 °C. Sr and Eu were introduced as chlorides, and I was introduced as NaI. The temperature dependence of both CO2 and CO production during the graphite oxidation measured […]
Gamma Spectrometry Examination of the AGR-3/4 Irradiation
The results from gamma spectrometry examination of the different components from the combined third and fourth U.S. Advanced Gas Reactor (AGR) TRISO-coated particle fuel irradiation tests (AGR-3/4) have been analyzed. This experiment was designed to provide information about in-pile fission product migration. In each of the 12 capsules, a single stack of four compacts with […]
AGR-2 TRISO Fuel Post-Irradiation Examination Final Report
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 engineering-scale coater. Work was also conducted on UO2 TRISO fuel produced for comparison with the AGR UCO fuel. Emphases we replaced on enumerating the frequency of SiC layer failures (failure […]