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Preliminary results of post-irradiation examination of the AGR-1 TRISO fuel compacts

Description: Five irradiated fuel compacts from the AGR-1 experiment have been examined in detail in order to assess in-pile fission product release behavior. Compacts were electrolytically deconsolidated and analyzed using the leach-burn-leach technique to measure fission product inventory in the compact matrix and identify any particles with a defective SiC layer. Loose particles were then gamma counted to measure the fission product inventory. One particle with a defective SiC layer was found in the five… more
Date: October 1, 2012
Creator: Demkowicz, Paul; Hunn, John; Morris, Robert; Harp, Jason; Winston, Philip; Baldwin, Charles et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Current Development Status of a Particle Size Analyzer for Coated Particle Fuel

Description: Work was performed to develop a prototype Particle Size Analyzer (PSA) for application to coated particle fuel characterization. This system was based on a light obscuration method and targeted towards high throughput analysis. Although never matured to the point of replacing existing lower throughput optical microscopy shadowgraph methods, the system was successfully applied to automating the counting of large particle samples for increased accuracy in calculating mean particle properties base… more
Date: August 1, 2007
Creator: Nelson, Andrew T; Hunn, John D & Karnowski, Thomas Paul
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

INERI-2006-003-F FY07 Annual Report

Description: Project Title: Comparison of Characterization Methods for Anisotropy and Microstructure of TRISO Particle Layers This INERI was created to support a comparative study between the newly developed two modulator generalized ellipsometry microscope (2-MGEM) at the Oak Ridge National Laboratory (ORNL) and the more traditional optical polarimeter (RAPAX) at the Commissariat l' nergie Atomique (CEA). These two systems are used to measure the anisotropy of the pyrocarbon layers in tri-isotropic (TRISO)… more
Date: October 1, 2007
Creator: Hunn, John D
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Key Differences in the Fabrication, Irradiation, and Safety Testing of U.S. and German TRISO-coated Particle Fuel and Their Implications on Fuel Performance

Description: High temperature gas reactor technology is achieving a renaissance around the world. This technology relies on high quality production and performance of coated particle fuel. Historically, the irradiation performance of TRISO-coated gas reactor particle fuel in Germany has been superior to that in the United States. German fuel generally displayed in-pile gas release values that were three orders of magnitude lower than U.S. fuel. Thus, we have critically examined the TRISO-coated fuel fabrica… more
Date: June 1, 2002
Creator: Petti, David Andrew; Maki, John Thomas; Buongiorno, Jacopo & Hobbins, Richard Redfield
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU04-02DTF

Description: This document is a compilation of coating and characterization data for the AGR-3/4 designed-to-fail (DTF) particles. The DTF coating is a high density, high anisotropy pyrocarbon coating of nominal 20 {micro}m thickness that is deposited directly on the kernel. The purpose of this coating is to fail early in the irradiation, resulting in a controlled release of fission products which can be analyzed to provide data on fission product transport. A small number of DTF particles will be included … more
Date: October 1, 2008
Creator: Hunn, John D & Miller, James Henry
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Accident Condition Simulator (FACS) Furnace for Post-Irradiation Heating Tests of VHTR Fuel Compacts

Description: Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as part of the Next Generation Nuclear Plant Fuels Development and Qualification Program. The PIE campaign will include extensive accident testing of irradiated very high temperature reactor fuel compacts to verify fission product retention characteristics at high temperatures. This work will be carried out at both the Idaho National Laboratory (INL) and the Oak Ridge National Laboratory, beginning wit… more
Date: October 1, 2010
Creator: Demkowicz, Paul A; Demkowicz, Paul & Laug, David V
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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