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Title: AGR-2 Irradiation Experiment Fission Product Mass Balance

Abstract

The Advanced Gas Reactor (AGR) program is in the process of qualifying tristructural isotropic (TRISO)-coated uranium carbide/uranium oxide (UCO) fuel for use in high-temperature gas-cooled reactors (HTGRs) in the United States. The second AGR irradiation (AGR-2) started in the Advanced Test Reactor (ATR) in June 2010 and was completed in October 2013. The first AGR irradiation (AGR-1) tested fuel produced on laboratory scale equipment, but the AGR-2 TRISO-coated fuel particles were produced on an industrial scale and then overcoated and compacted into cylindrical compacts using laboratory-scale processes. Both UCO and UO2 fuels were irradiated in AGR-2 so that their performance could be compared. The UCO fuel was in Capsules 2, 5, and 6, and the UO2 fuel was in Capsule 3. (Capsules 1 and 4 were French and South African fuel, respectively. These fuels will not be discussed.) UCO burnups ranged from 7.3 to 13.2 % fissions per initial metal atom (FIMA), and compact time-averaged, volume-averaged (TAVA) irradiation temperatures ranged from about 1000°C to 1300°C. UO2 compact burnups ranged from 9.0 to 10.7 % FIMA, and compact TAVA temperatures ranged from about 1000 to 1060°C.

Authors:
 [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1508379
Report Number(s):
INL/EXT-19-53559-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Program Document
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Advanced Gas Reactor; Hot Fuel Examination Facility; tristructural isotropic

Citation Formats

Stempien, John D. AGR-2 Irradiation Experiment Fission Product Mass Balance. United States: N. p., 2019. Web.
Stempien, John D. AGR-2 Irradiation Experiment Fission Product Mass Balance. United States.
Stempien, John D. Tue . "AGR-2 Irradiation Experiment Fission Product Mass Balance". United States. https://www.osti.gov/servlets/purl/1508379.
@article{osti_1508379,
title = {AGR-2 Irradiation Experiment Fission Product Mass Balance},
author = {Stempien, John D},
abstractNote = {The Advanced Gas Reactor (AGR) program is in the process of qualifying tristructural isotropic (TRISO)-coated uranium carbide/uranium oxide (UCO) fuel for use in high-temperature gas-cooled reactors (HTGRs) in the United States. The second AGR irradiation (AGR-2) started in the Advanced Test Reactor (ATR) in June 2010 and was completed in October 2013. The first AGR irradiation (AGR-1) tested fuel produced on laboratory scale equipment, but the AGR-2 TRISO-coated fuel particles were produced on an industrial scale and then overcoated and compacted into cylindrical compacts using laboratory-scale processes. Both UCO and UO2 fuels were irradiated in AGR-2 so that their performance could be compared. The UCO fuel was in Capsules 2, 5, and 6, and the UO2 fuel was in Capsule 3. (Capsules 1 and 4 were French and South African fuel, respectively. These fuels will not be discussed.) UCO burnups ranged from 7.3 to 13.2 % fissions per initial metal atom (FIMA), and compact time-averaged, volume-averaged (TAVA) irradiation temperatures ranged from about 1000°C to 1300°C. UO2 compact burnups ranged from 9.0 to 10.7 % FIMA, and compact TAVA temperatures ranged from about 1000 to 1060°C.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {4}
}

Program Document:
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