AGR 3/4 Irradiation Test Final As Run Report

Collin, Blaise P.

doi:10.2172/1196553

Cited by 17 publications

(32 citation statements)

References 12 publications

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“…Figure 1 shows that AGR-3/4 spanned a burnup range from approximately 4.8 to 15.25 % FIMA and compact TAVA irradiation temperatures from approximately 830 to 1375°C. AGR-3/4 was irradiated in the northeast flux trap of ATR, from December 2011 to April 2014 (Collin 2015b). The experiment consisted of fuel compacts containing TRISO-coated driver-fuel particles similar to AGR-1 baseline fuel (Collin 2015b;Hunn and Lowden 2007;Hunn et al 2014) and designed-to-fail (DTF) particles that are designed to release fission products during irradiation, which will migrate through the surrounding cylindrical rings of graphitic matrix and nuclear-grade graphite.…”

Section: Status Of Agr Program Irradiationsmentioning

confidence: 99%

AGR-3/4 Experiment Preliminary Mass Balance

Stempien

Demkowicz

Harp

et al. 2018

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Section: Status Of Agr Program Irradiationsmentioning

confidence: 99%

AGR-3/4 Experiment Preliminary Mass Balance

Stempien

Demkowicz

Harp

et al. 2018

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“…The AGR-3/4 test train was designed for insertion in the northeast flux trap of the ATR. Unlike the Large B positions used for the AGR-1 and AGR-2 irradiations, the northeast flux trap minimizes the radial neutron flux gradient, provides a high neutron flux, and features a larger diameter (Collin 2015a). Figure 1 shows the test train stack of 12 sample capsules containing different types of graphite.…”

Section: Test Train Constructionmentioning

confidence: 99%

“…AGR-3/4 combined the third and fourth experiments in the AGR series to test TRISO-coated lowenriched uranium oxycarbide fuel. This experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport (Collin 2015a, Collin 2015b. The experiment featured fuel compacts loaded with TRISO-coated particles having UCO kernel diameters similar to those in AGR-1 and TRISO coating thicknesses similar to those in AGR-2.…”

Section: Introductionmentioning

confidence: 99%

“…These data can then be used to determine the diffusion coefficients and other transport parameters for the fission products within graphitic matrix and nuclear-grade graphite. AGR-3/4 fuel compacts were irradiated to the targeted burnup and fast fluence ranges, despite termination of the experiment slightly before its initial target of 400 effective full power days (Collin 2015a, Collin 2015b. Out of 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy metal atom (FIMA).…”

Section: Introductionmentioning

confidence: 99%

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AGR-3/4 Irradiation Test Train Disassembly and Component Metrology First Look Report

Stempien

Rice

Harp

et al. 2016

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The Advanced Gas Reactor (AGR)-3/4 experiment was designed to study fission product transport within graphitic matrix material and nuclear-grade graphite. To this end, this experiment consisted of 12 capsules, each fueled with 4 compacts containing uranium oxycarbide (UCO) tri-structural isotropic (TRISO)-coated particles as driver fuel and 20 UCO designed-to-fail (DTF) fuel particles in each compact. The DTF fuel was fabricated with a thin pyrocarbon layer that was intended to fail during irradiation and provide a known source of fission products. These fission products could then migrate through the compact and into the surrounding concentric rings of graphitic matrix material and/or nuclear-grade graphite. Through post-irradiation examination (PIE) of the rings (including physical sampling and gamma scanning) fission product concentration profiles within the rings can be determined. These data can be used to elucidate fission product transport parameters (e.g., diffusion coefficients within the test materials) which will be used to inform and refine models of fission product transport. After irradiation in the Advanced Test Reactor (ATR) had been completed in April 2014, the AGR-3/4 experiment was shipped to the Hot Fuel Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) for inspection, disassembly, and metrology. The AGR-3/4 test train was received at MFC in two separate shipments between February and April 2015. Visual examinations of the test train exterior did not indicate dimensional distortion, and only two small discolored areas were observed at the bottom of Capsules 8 and 9. Despite slight external discoloration, no corresponding discoloration was found on the inside of these capsules. Prior to disassembly, the two test train sections were subject to analysis via the Precision Gamma Scanner (PGS), which did not indicate that any gross fuel relocation had occurred. A series of specialized tools, including clamps, cutters, and drills, had been designed and fabricated to carry out test train disassembly and recovery of capsule components (graphite rings and fuel compacts). This equipment performed well for separating each capsule in the test train and extracting the capsule components. Only a few problems were encountered. In one case, the outermost ring (the sink ring) was cracked during removal of the capsule through tubes. Although the sink ring will be analyzed to obtain a mass-balance of fission products in the experiment, these cracks do not pose a major concern because the sink ring will not be analyzed for its fission product spatial distribution. In Capsules 4 and 5, the compacts could not be removed from the inner rings using standard methods. An arbor press was modified and used to successfully remove the compacts from the inner rings without damaging the rings. Dimensional measurements were made on the compacts, inner rings, outer rings, and sink rings. The diameters of all compacts decreased by 0.5 to 2.0%. Generally, the extent of compact diametric shrinkage increased with...

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“…These were combined into a single experiment to reduce costs and overall program schedule. Details are found in Reference [17]. The objective of this experiment is very different than the objectives of AGR-1 or AGR-2.…”

Section: Agr-3/4mentioning

confidence: 99%

A summary of the results from the DOE advanced gas reactor (AGR) fuel development and qualification program

Petti

2017

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AGR 3/4 Irradiation Test Final As Run Report

Cited by 17 publications

References 12 publications

AGR-3/4 Experiment Preliminary Mass Balance

AGR-3/4 Experiment Preliminary Mass Balance

AGR-3/4 Irradiation Test Train Disassembly and Component Metrology First Look Report

A summary of the results from the DOE advanced gas reactor (AGR) fuel development and qualification program

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