AGR-1 Post Irradiation Examination Final Report

Demkowicz, Paul A.

doi:10.2172/1236801

Cited by 47 publications

(47 citation statements)

References 34 publications

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“…However, the fraction of particles in each subset did not correspond to the fraction of AGR-1 B particles with larger or smaller microstructure. [30,35,36]. Similar bi-modal particle-to-particle silver release variations were also noted for AGR-1 V1, which had a homogenous SiC layer microstructure [6,37].…”

Section: Irradiated Triso Fuel Performancesupporting

confidence: 63%

“…AGR-1 PIE efforts measured individual particle fission product inventories and identified a broad distribution in fission product retention behavior for 110m Ag in a single compact and this behavior was observed for all variants in the AGR-1 fuel irradiation. Post-irradiation examination of the SiC microstructure of high release particles and low release particles in AGR-1 B compacts indicated no obvious correlation to the outlier fine-grained batch of AGR-1 B-45T[30].…”

mentioning

confidence: 89%

“…Significant PIE efforts at ORNL and INL have been conducted on AGR-1 fuel compacts [30], with PIE on AGR-2 fuel compacts being initiated in 2015. PIE analysis of irradiated AGR-1 fuel indicated compacts containing particles from all AGR-1 variants released 110m Ag.…”

Section: Irradiated Triso Fuel Performancementioning

confidence: 99%

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SiC layer microstructure in AGR-1 and AGR-2 TRISO fuel particles and the influence of its variation on the effective diffusion of key fission products

Gerczak

Hunn

Lowden

et al. 2016

Journal of Nuclear Materials

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Tristructural isotropic (TRISO) coated particle fuel is a promising fuel form for advanced reactor concepts such as high temperature gas-cooled reactors (HTGR) and is being developed domestically under the US Department of Energy's Nuclear Reactor Technologies Initiative in support of Advanced Reactor Technologies. The fuel development and qualification plan includes a series of fuel irradiations to demonstrate fuel performance from the laboratory to commercial scale. The first irradiation campaign, AGR-1, included four separate TRISO fuel variants composed of multiple, laboratory-scale coater batches. The second irradiation campaign, AGR-2, included TRISO fuel particles fabricated by BWX Technologies with a larger coater representative of an industrial-scale system. The SiC layers of as-fabricated particles from the AGR-1 and AGR-2 irradiation campaigns have been investigated by electron backscatter diffraction (EBSD) to provide key information about the microstructural features relevant to fuel performance. The results of a comprehensive study of multiple particles from all constituent batches are reported. The observations indicate that there were microstructural differences between variants and among constituent batches in a single variant. Insights on the influence of microstructure on the effective diffusivity of key fission products in the SiC layer are also discussed.

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Section: Irradiated Triso Fuel Performancesupporting

confidence: 63%

mentioning

confidence: 89%

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SiC layer microstructure in AGR-1 and AGR-2 TRISO fuel particles and the influence of its variation on the effective diffusion of key fission products

Gerczak

Hunn

Lowden

et al. 2016

Journal of Nuclear Materials

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“…Because AGR-1 is the first irradiation of its kind in the NGNP project and involves a complex, multi-capsule, instrumented lead experiment containing four different types of fuel, PIE also will seek to investigate the performance of the test train and components. The specific objectives and planned PIE activities for the AGR-1 experiment are presented in the AGR-1 PIE plan (Demkowicz 2010). The test train was shipped to the Materials and Fuels Complex (MFC) at the Idaho National Laboratory (INL) for PIE in March 2010.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Fission Products on the AGR-1 Capsule Components

Demkowicz¹,

Harp²,

Winston³

et al. 2013

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SUMMARYThe components of the Advanced Gas Reactor (AGR)-1 irradiation capsules were analyzed to measure the retained inventory of fission products in order to determine the extent of in-pile fission product release from the fuel compacts. This includes analysis of (1) the metal capsule components, (2) the graphite fuel holders, (3) the graphite spacers, and (4) the gas exit lines. The fission products most prevalent in the components were Ag-110m, Cs-134, Cs-137, Eu-154, and Sr-90, and the most common locations were the metal capsule components and the graphite fuel holders. Gamma scanning of the graphite fuel holders also was performed to determine spatial distribution of Ag-110m and radiocesium.

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“…In aim to understand the neutron irradiation effects on TRISO coated particles and the fission product mechanisms, micro-and nano-characterization has been performed. This paper provides selected results from an AGR-2 particle (AGR2-223-RS06, irradiated at a time-average volume-average temperature [TAVA] of 1161°C; to burnup of 10.8 % fissions of initial metal atoms [FIMA]) and AGR-1 particles (AGR1-632-035 or AGR1-632-034) with a similar irradiation history (1070°C TAVA; 11.4% FIMA) [3] [4].…”

mentioning

confidence: 99%