Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4

Hunn, John D.; Montgomery, Fred C.; Skitt, Darren J.; Helmreich, Grant W.

doi:10.2172/1709104

Cited by 3 publications

(4 citation statements)

References 12 publications

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“…In the central region of the compact, where the DTF particles reside, this method gives the fission product inventory retained in the DTF particles, plus that in the fuel compact matrix, and the OPyC of driver-fuel particles surrounding the DTF particles. Some reports detailing the radial deconsolidation work are complete (Hunn et al 2020;Helmreich et al 2021 and, others are in progress with preliminary results included here.…”

Section: Fuel Compact Radial Deconsolidationmentioning

confidence: 99%

“…The TAVA irradiation temperature of the compacts, inner, outer, and SRs were 1191, 1038, 971, and 646℃ respectively (Hawkes 2016), and the calculated axial variation in temperature was less than 129℃ for the compacts, 34℃ for the IR and 12℃ for the OR. R-DLBL was carried out on Compacts 10-1, 10-2 and 10-4, though these capsules were the subject of heating tests at 1400℃ and 1200℃ respectively before deconsolidation (Hunn et al 2020), which will need to be incorporated into the models before valid comparisons can be made.…”

Section: Capsule 10mentioning

confidence: 99%

“…The results of this approach are shown in Figure 7, where the 134 Cs and 137 Cs measurements from Compacts 1-3 and 1-4 (Hunn et al 2020) and the overall 134 Cs and 137 Cs IR inventory from the mass balance report (Stempien et al 2018) were fit together to simultaneously obtain a temperature-dependent diffusivity and sorptivity. It is clear from the model fit that Fickian diffusion through the IR is not the primary source of activity in the OR and SR.…”

Section: Finite-element Radial Diffusion Modelmentioning

confidence: 99%

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Status of Modifications to the AGR-3/4 Fission Product Transport Model

Riet

2023

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Section: Fuel Compact Radial Deconsolidationmentioning

confidence: 99%

Section: Capsule 10mentioning

confidence: 99%

Section: Finite-element Radial Diffusion Modelmentioning

confidence: 99%

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Status of Modifications to the AGR-3/4 Fission Product Transport Model

Riet

2023

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“…However, the AGR-3/4 compact PIE was not performed by dissolution of the entire fuel sample. Because this experiment used DTF fuel specimens, PIE included the radial deconsolidation of individual compacts to segment the compacts into separate collections of particles and matrix debris from concentric cylindrical volumes, each of which was subjected to a leach-burn-leach analysis to quantify the actinides and fission products released by the driver fuel and DTF particles [56]. This experiment configuration was significantly different from that of the AGR-1 and AGR-2 tests and is illustrated in Figure 12.…”

Section: Agr-2mentioning

confidence: 99%

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

DeHart

Bess²,

Ilas

2023

JNE

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Many advanced reactor concept designs rely on high-assay low-enriched uranium (HALEU) fuel, enriched up to approximately 19.75% 235U by weight. Efforts are underway by the US government to increase HALEU production in the United States to meet anticipated needs. However, very few data exist for validation of computational models that include HALEU, beyond a few fresh fuel benchmark specifications in the International Reactor Physics Experiment Evaluation Project. Nevertheless, there are other data with potential value available for developing into quality benchmarks for use in data- and software-validation efforts. This paper reviews the available evaluated HALEU fuel benchmarks and some of the potentially relevant benchmarks for fresh highly enriched uranium. It then introduces experimental data for HALEU fuel irradiated at Idaho National Laboratory, from relatively recent irradiation programs at the Advanced Test Reactor. Such data should be evaluated and, if valuable, collected into detailed benchmark specifications to meet the needs of HALEU-based reactor designers.

show abstract

A Review of a Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

DeHart¹,

Bess²,

Ilas³

2023

Preprint

View full text Add to dashboard Cite

Many advanced reactor concept designs rely on high-assay low-enriched uranium (HALEU) fuel, enriched up to approximately 19.75% 235U by weight. Efforts are underway by the US government to increase HALEU production in the United States to meet anticipated needs. However, very little data exists for validation of computational models that include HALEU, beyond a few fresh fuel benchmark specifications in the International Reactor Physics Experiment Evaluation Project. Nevertheless, there is other data with potential value available for developing into quality benchmarks for use in data and software validation efforts. This paper reviews the available evaluated HALEU fuel benchmarks and some of the potentially relevant benchmarks for fresh highly enriched uranium. It then introduces experimental data for HALEU fuel irradiated at Idaho National Laboratory, from relatively recent irradiation programs at the Advanced Test Reactor. Such data should be evaluated and, if valuable, collected into detailed benchmark specifications to meet the needs of HALEU-based reactor designers.

show abstract

Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4

Cited by 3 publications

References 12 publications

Status of Modifications to the AGR-3/4 Fission Product Transport Model

Status of Modifications to the AGR-3/4 Fission Product Transport Model

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

A Review of a Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

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