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Title: Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor

Abstract

The United States Department of Energy’s Very High Temperature Reactor Technology Development Office (VHTR-TDO) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is irradiating up to seven low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation high temperature gas-cooled reactors in the United States. The experiments will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of several independent capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performancemore » of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and was completed in November 2009. The second experiment (AGR-2) started irradiation in June 2010 and completed in October 2013. The third and fourth experiments were combined into a single experiment designated (AGR-3/4), which started its irradiation in December 2011 and completed in April 2014. Since the purpose of this combined experiment was to provide data on fission product migration and retention in a high temperature gas-cooled reactor (HTGR), the design of this experiment was significantly different from the first two experiments, though the control and monitoring systems are extremely similar. The design of the experiment will be discussed followed by its progress and status to date.« less

Authors:
; ; ORCiD logo
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1173096
Report Number(s):
INL/CON-14-32154
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: HTR-2014,Weihai, China,10/27/2014,10/31/2014
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AGR; HTGR; TRISO

Citation Formats

Davenport, Michael E., Palmer, A. Joseph, and Petti, David A. Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor. United States: N. p., 2001. Web.
Davenport, Michael E., Palmer, A. Joseph, & Petti, David A. Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor. United States.
Davenport, Michael E., Palmer, A. Joseph, and Petti, David A. 2001. "Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor". United States. https://www.osti.gov/servlets/purl/1173096.
@article{osti_1173096,
title = {Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor},
author = {Davenport, Michael E. and Palmer, A. Joseph and Petti, David A.},
abstractNote = {The United States Department of Energy’s Very High Temperature Reactor Technology Development Office (VHTR-TDO) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is irradiating up to seven low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation high temperature gas-cooled reactors in the United States. The experiments will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of several independent capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and was completed in November 2009. The second experiment (AGR-2) started irradiation in June 2010 and completed in October 2013. The third and fourth experiments were combined into a single experiment designated (AGR-3/4), which started its irradiation in December 2011 and completed in April 2014. Since the purpose of this combined experiment was to provide data on fission product migration and retention in a high temperature gas-cooled reactor (HTGR), the design of this experiment was significantly different from the first two experiments, though the control and monitoring systems are extremely similar. The design of the experiment will be discussed followed by its progress and status to date.},
doi = {},
url = {https://www.osti.gov/biblio/1173096}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Oct 01 00:00:00 EDT 2001},
month = {Mon Oct 01 00:00:00 EDT 2001}
}

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