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Title: Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1

Abstract

Post-irradiation examination (PIE) and elevated-temperature safety testing are being performed on tristructural-isotropic (TRISO) coated-particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program second irradiation experiment (AGR-2). Details on this irradiation experiment have been previously reported [Collin 2014]. The AGR-2 PIE effort builds upon the understanding acquired throughout the AGR-1 PIE campaign [Demkowicz et al. 2015] and is establishing a database for the different AGR-2 fuel designs.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1]
  1. 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 Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7)
OSTI Identifier:
1376621
Report Number(s):
ORNL/TM-2017/439
101951
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Hunn, John D., Morris, Robert N., Baldwin, Charles A., Burns, Zachary M., Montgomery, Fred C., and Skitt, Darren J. Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1. United States: N. p., 2017. Web. doi:10.2172/1376621.
Hunn, John D., Morris, Robert N., Baldwin, Charles A., Burns, Zachary M., Montgomery, Fred C., & Skitt, Darren J. Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1. United States. doi:10.2172/1376621.
Hunn, John D., Morris, Robert N., Baldwin, Charles A., Burns, Zachary M., Montgomery, Fred C., and Skitt, Darren J. Tue . "Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1". United States. doi:10.2172/1376621. https://www.osti.gov/servlets/purl/1376621.
@article{osti_1376621,
title = {Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1},
author = {Hunn, John D. and Morris, Robert N. and Baldwin, Charles A. and Burns, Zachary M. and Montgomery, Fred C. and Skitt, Darren J.},
abstractNote = {Post-irradiation examination (PIE) and elevated-temperature safety testing are being performed on tristructural-isotropic (TRISO) coated-particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program second irradiation experiment (AGR-2). Details on this irradiation experiment have been previously reported [Collin 2014]. The AGR-2 PIE effort builds upon the understanding acquired throughout the AGR-1 PIE campaign [Demkowicz et al. 2015] and is establishing a database for the different AGR-2 fuel designs.},
doi = {10.2172/1376621},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Aug 01 00:00:00 EDT 2017},
month = {Tue Aug 01 00:00:00 EDT 2017}
}

Technical Report:

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