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Title: Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment

Abstract

Ceramography was performed on cross sections from four tristructural isotropic (TRISO) coated particle fuel compacts taken from the AGR-2 experiment, which was irradiated between June 2010 and October 2013 in the Advanced Test Reactor (ATR). The fuel compacts examined in this study contained TRISO-coated particles with either uranium oxide (UO2) kernels or uranium oxide/uranium carbide (UCO) kernels that were irradiated to final burnup values between 9.0 and 11.1% FIMA. These examinations are intended to explore kernel and coating morphology evolution during irradiation. This includes kernel porosity, swelling, and migration, and irradiation-induced coating fracture and separation. Variations in behavior within a specific cross section, which could be related to temperature or burnup gradients within the fuel compact, are also explored. The criteria for categorizing post-irradiation particle morphologies developed for AGR-1 ceramographic exams, was applied to the particles in the AGR-2 compacts particles examined. Results are compared with similar investigations performed as part of the earlier AGR-1 irradiation experiment. This paper presents the results of the AGR-2 examinations and discusses the key implications for fuel irradiation performance.

Authors:
 [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1364473
Report Number(s):
INL/EXT-16-39462
TRN: US1703369
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; URANIUM DIOXIDE; URANIUM; TEST REACTORS; URANIUM CARBIDES; CERAMOGRAPHY; COMPARATIVE EVALUATIONS; CROSS SECTIONS; FUEL PARTICLES; AGR; Fuel; TRISO

Citation Formats

Rice, Francine Joyce, and Stempien, John Dennis. Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment. United States: N. p., 2016. Web. doi:10.2172/1364473.
Rice, Francine Joyce, & Stempien, John Dennis. Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment. United States. doi:10.2172/1364473.
Rice, Francine Joyce, and Stempien, John Dennis. Thu . "Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment". United States. doi:10.2172/1364473. https://www.osti.gov/servlets/purl/1364473.
@article{osti_1364473,
title = {Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment},
author = {Rice, Francine Joyce and Stempien, John Dennis},
abstractNote = {Ceramography was performed on cross sections from four tristructural isotropic (TRISO) coated particle fuel compacts taken from the AGR-2 experiment, which was irradiated between June 2010 and October 2013 in the Advanced Test Reactor (ATR). The fuel compacts examined in this study contained TRISO-coated particles with either uranium oxide (UO2) kernels or uranium oxide/uranium carbide (UCO) kernels that were irradiated to final burnup values between 9.0 and 11.1% FIMA. These examinations are intended to explore kernel and coating morphology evolution during irradiation. This includes kernel porosity, swelling, and migration, and irradiation-induced coating fracture and separation. Variations in behavior within a specific cross section, which could be related to temperature or burnup gradients within the fuel compact, are also explored. The criteria for categorizing post-irradiation particle morphologies developed for AGR-1 ceramographic exams, was applied to the particles in the AGR-2 compacts particles examined. Results are compared with similar investigations performed as part of the earlier AGR-1 irradiation experiment. This paper presents the results of the AGR-2 examinations and discusses the key implications for fuel irradiation performance.},
doi = {10.2172/1364473},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 2016},
month = {Thu Sep 01 00:00:00 EDT 2016}
}

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