The AGR-3/4 fission product transport irradiation experiment

Collin, Blaise P.; Demkowicz, Paul A.; Petti, David A.; Hawkes, Grant L.; Palmer, Joe; Pham, Binh T.; Scates, Dawn M.; Sterbentz, James W.

doi:10.1016/j.nucengdes.2017.12.016

Cited by 13 publications

(17 citation statements)

References 9 publications

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“…Each capsule had its own gas line, and a sweep gas carried fission gases to gamma detectors. Fission gas measurements taken during the AGR-3/4 irradiation, and release-to-birth ratio analysis enabled estimates of the number of in-pile DTF particle failures per irradiation capsule (Collin et al 2018). These estimates are listed in Table 2.…”

Section: Capsulementioning

confidence: 99%

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AGR-3/4 Experiment Preliminary Mass Balance

Stempien

Demkowicz

Harp

et al. 2018

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Section: Capsulementioning

confidence: 99%

“…Table valuesfrom(Collin et al 2018). ....................................................................................................................... Table 3.…”

mentioning

confidence: 99%

AGR-3/4 Experiment Preliminary Mass Balance

Stempien

Demkowicz

Harp

et al. 2018

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“…Online fission gas monitoring was used for each capsule during the AGR-3/4 irradiation in ATR (Collin et al 2018). Using fission gas measurements, estimates of the number of DTF particles to fail inpile (with broken pyrocarbon layers) in each of the 12 AGR-3/4 irradiation capsules were made .…”

Section: Compact Selection Processmentioning

confidence: 99%

“…AGR-3/4 DTF particle failure count in each irradiation capsule(Collin et al 2018). .................... …”

mentioning

confidence: 99%

AGR-3/4 TRISO Fuel Compact Ceramography

Stempien

Schulthess

2020

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The combined third and fourth irradiation in the Advanced Gas Reactor (AGR) program (AGR-3/4) contained tristructural isotropic (TRISO)-coated particle fuel and designed-to-fail (DTF) fuel particles. The DTF particles were only coated with highly anisotropic pyrocarbon (PyC) so they would purposely fail during the AGR-3/4 irradiation and provide a source of fission products for measurement. Frickey performed materialographic preparation of the irradiated and unirradiated fuel compacts. This included designing and fabricating the mounts, grinding, and polishing the mounts at the Hot Fuel Examination Facility at Idaho National Laboratory. Cassie Anderson-Thueson assisted in the mounting, grinding, polishing, and optical microscopy work. John Stanek and Francine Rice assisted in the mount design and provided valuable input to sample preparation and microscopy processes leading to acquisition of the images included in this report. Fuel burnup and fast neutron fluence were calculated by Dr. Jim Sterbentz. Fuel temperatures and temperature variations were calculated by Grant Hawkes.

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“…AGR-3/4 is the combination of the third and fourth planned experiments to test TRISO-coated lowenriched uranium fuel. A detailed description of the experiment and results are provided in (Collin et al, 2018). Figure 7 depicts a schematic view of AGR-3/4 capsules.…”

Section: Advanced Gas Reactor-3/4 Irradiationmentioning

confidence: 99%

AGR-1, AGR-2 and AGR-3/4 Release-to-Birth Ratio Data Analysis

Pham

Scates

2019

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The AGR-3/4 fission product transport irradiation experiment

Cited by 13 publications

References 9 publications

AGR-3/4 Experiment Preliminary Mass Balance

AGR-3/4 Experiment Preliminary Mass Balance

AGR-3/4 TRISO Fuel Compact Ceramography

AGR-1, AGR-2 and AGR-3/4 Release-to-Birth Ratio Data Analysis

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