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Title: Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results

Abstract

Abstract – The AGR-1 irradiation experiment contains seventy-two individual cylindrical fuel compacts (25 mm long x 12.5 mm diameter) each containing approximately 4100 TRISO-coated uranium oxycarbide fuel particles. The experiment accumulated 620 effective full power days in the Advanced Test Reactor at the Idaho National Laboratory with peak burnups exceeding 19% FIMA. An extensive post-irradiation examination campaign will be performed on the AGR-1 fuel in order to characterize the irradiated fuel properties, assess the in-pile fuel performance in terms of coating integrity and fission metals release, and determine the fission product retention behavior during high temperature accident testing. PIE experiments will include dimensional measurements of fuel and irradiated graphite, burnup measurements, assessment of fission metals release during irradiation, evaluation of coating integrity using the leach-burn-leach technique, microscopic examination of kernel and coating microstructures, and accident testing of the fuel in helium at temperatures up to 1800°C. Activities completed to date include opening of the irradiated capsules, measurement of fuel dimensions, and gamma spectrometry of selected fuel compacts.

Authors:
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1004269
Report Number(s):
INL/CON-10-19184
TRN: US1100648
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: HTR 2010,Prague, Czech Republic,10/18/2010,10/20/2010
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACCIDENTS; BURNUP; COATINGS; DIMENSIONS; FISSION; FISSION PRODUCTS; FUEL PARTICLES; GAMMA SPECTROSCOPY; GRAPHITE; HELIUM; IRRADIATION; KERNELS; OXYCARBIDES; POST-IRRADIATION EXAMINATION; RETENTION; SPENT FUELS; TEST REACTORS; TESTING; URANIUM; NGNP+TDO+VHTR+R&D+Fuel+AGR-1+AGR-2+Irradiation+Fis

Citation Formats

Demkowicz, Paul. Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results. United States: N. p., 2001. Web.
Demkowicz, Paul. Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results. United States.
Demkowicz, Paul. 2001. "Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results". United States. https://www.osti.gov/servlets/purl/1004269.
@article{osti_1004269,
title = {Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results},
author = {Demkowicz, Paul},
abstractNote = {Abstract – The AGR-1 irradiation experiment contains seventy-two individual cylindrical fuel compacts (25 mm long x 12.5 mm diameter) each containing approximately 4100 TRISO-coated uranium oxycarbide fuel particles. The experiment accumulated 620 effective full power days in the Advanced Test Reactor at the Idaho National Laboratory with peak burnups exceeding 19% FIMA. An extensive post-irradiation examination campaign will be performed on the AGR-1 fuel in order to characterize the irradiated fuel properties, assess the in-pile fuel performance in terms of coating integrity and fission metals release, and determine the fission product retention behavior during high temperature accident testing. PIE experiments will include dimensional measurements of fuel and irradiated graphite, burnup measurements, assessment of fission metals release during irradiation, evaluation of coating integrity using the leach-burn-leach technique, microscopic examination of kernel and coating microstructures, and accident testing of the fuel in helium at temperatures up to 1800°C. Activities completed to date include opening of the irradiated capsules, measurement of fuel dimensions, and gamma spectrometry of selected fuel compacts.},
doi = {},
url = {https://www.osti.gov/biblio/1004269}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Oct 01 00:00:00 EDT 2001},
month = {Mon Oct 01 00:00:00 EDT 2001}
}

Conference:
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