AGR-1 Irradiation Test Final As-Run Report

Collin, Blaise P.

doi:10.2172/1468990

Cited by 26 publications

(32 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It is probable that the release observed across all compacts in-pile was driven primarily by in-reactor variables. The likely dominant in-reactor variable driving fission product release during the AGR-1 experiment was temperature, where temperature varied spatially across compacts and temporally during the irradiation by up to ~300°C [38]. This temperature variation across the compact provides the most direct explanation of the particle-to-particle difference in release behavior under a diffusion-driven release mechanism.…”

Section: Irradiated Triso Fuel Performancementioning

confidence: 98%

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

View full text Add to dashboard Cite

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.

show abstract

Section: Irradiated Triso Fuel Performancementioning

confidence: 98%

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

View full text Add to dashboard Cite

show abstract

“…X indicates the capsule, Y indicates the vertical level within the capsule, and Z indicates the stack as described in Reference 5. The experiment completed 620 effective full power days in the reactor and achieved a compact-average peak burnup of 19.6% fissions per initial heavy metal atom (FIMA) with zero TRISO coating failures observed based on the measured fission gas release-to-birth ratios during the irradiation [22,23].…”

Section: Agr-1 Fuel and Irradiationmentioning

confidence: 99%

First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace

Demkowicz

Reber

Scates

et al. 2015

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

Three TRISO fuel compacts from the AGR-1 irradiation experiment were subjected to safety tests at 1600 and 1800°C for approximately 300 h to evaluate the fission product retention characteristics. Silver behavior was dominated by rapid release of an appreciable fraction of the compact inventory (3 to 34%) at the beginning of the tests, believed to be from inventory residing in the compact matrix and outer pyrocarbon (OPyC) prior to the safety test.

show abstract

“…Table 1 lists the fuel types for each capsule. The experiment was irradiated for 620 effective full-power days in the ATR and achieved a calculated compact average peak burnup of 19.5% fissions per initial heavy metal atom, with zero particle failures observed based on the measured fission gas release-to-birth ratios (Collin 2012). The time-average volume average temperature for the fuel compacts ranged from 955 to 1136°C and the time-average maximum temperature ranged from 1069 to 1197°C (Hawkes 2012).…”

Section: Introductionmentioning

confidence: 99%

Analysis of Fission Products on the AGR-1 Capsule Components

Demkowicz¹,

Harp²,

Winston³

et al. 2013

View full text Add to dashboard Cite

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.

show abstract

AGR-1 Irradiation Test Final As-Run Report

Cited by 26 publications

References 0 publications

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

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

First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace

Analysis of Fission Products on the AGR-1 Capsule Components

Contact Info

Product

Resources

About