U.S. Department of EnergyOffice of Scientific and Technical Information
PIE on Safety-Tested AGR-1 Compact 5-1-1
Abstract
Post-irradiation examination (PIE) is being performed in support of tristructural isotropic (TRISO) coated particle fuel development and qualification for High-Temperature Gas-cooled Reactors (HTGRs). AGR-1 was the first in a series of TRISO fuel irradiation experiments initiated in 2006 under the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program; this work continues to be funded by the Department of Energy's Office of Nuclear Energy as part of the Advanced Reactor Technologies (ART) initiative. AGR-1 fuel compacts were fabricated at Oak Ridge National Laboratory (ORNL) in 2006 and irradiated for three years in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) to demonstrate and evaluate fuel performance under HTGR irradiation conditions. PIE is being performed at INL and ORNL to study how the fuel behaved during irradiation, and to examine fuel performance during exposure to elevated temperatures at or above temperatures that could occur during a depressurized conduction cooldown event. This report summarizes safety testing of irradiated AGR-1 Compact 5-1-1 in the ORNL Core Conduction Cooldown Test Facility (CCCTF) and post-safety testing PIE.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1213349
- Report Number(s):
- ORNL/TM-2015/317
- DOE Contract Number:
- AC05-00OR22725
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- TRISO; Coated Particle Fuel; AGR; PIE
Citation Formats
Hunn, John D., Morris, Robert Noel, Baldwin, Charles A., Montgomery, Fred C., and Gerczak, Tyler J. PIE on Safety-Tested AGR-1 Compact 5-1-1. United States: N. p., 2015.
Web. doi:10.2172/1213349.
Hunn, John D., Morris, Robert Noel, Baldwin, Charles A., Montgomery, Fred C., & Gerczak, Tyler J. PIE on Safety-Tested AGR-1 Compact 5-1-1. United States. https://doi.org/10.2172/1213349
Hunn, John D., Morris, Robert Noel, Baldwin, Charles A., Montgomery, Fred C., and Gerczak, Tyler J. 2015.
"PIE on Safety-Tested AGR-1 Compact 5-1-1". United States. https://doi.org/10.2172/1213349. https://www.osti.gov/servlets/purl/1213349.
@article{osti_1213349,
title = {PIE on Safety-Tested AGR-1 Compact 5-1-1},
author = {Hunn, John D. and Morris, Robert Noel and Baldwin, Charles A. and Montgomery, Fred C. and Gerczak, Tyler J.},
abstractNote = {Post-irradiation examination (PIE) is being performed in support of tristructural isotropic (TRISO) coated particle fuel development and qualification for High-Temperature Gas-cooled Reactors (HTGRs). AGR-1 was the first in a series of TRISO fuel irradiation experiments initiated in 2006 under the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program; this work continues to be funded by the Department of Energy's Office of Nuclear Energy as part of the Advanced Reactor Technologies (ART) initiative. AGR-1 fuel compacts were fabricated at Oak Ridge National Laboratory (ORNL) in 2006 and irradiated for three years in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) to demonstrate and evaluate fuel performance under HTGR irradiation conditions. PIE is being performed at INL and ORNL to study how the fuel behaved during irradiation, and to examine fuel performance during exposure to elevated temperatures at or above temperatures that could occur during a depressurized conduction cooldown event. This report summarizes safety testing of irradiated AGR-1 Compact 5-1-1 in the ORNL Core Conduction Cooldown Test Facility (CCCTF) and post-safety testing PIE.},
doi = {10.2172/1213349},
url = {https://www.osti.gov/biblio/1213349},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Aug 01 00:00:00 EDT 2015},
month = {Sat Aug 01 00:00:00 EDT 2015}
}