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Title: Irradiation of Miniature Fuel Specimens in the High Flux Isotope Reactor

Abstract

The Advanced Fuels Campaign (AFC) within the US Department of Energy (DOE) Office of Nuclear Energy is considering several advanced ceramic fuels for use in light water reactors (LWRs) and/or advanced reactor concepts. Advanced fuels, such as uranium carbide (UC), uranium nitride (UN), and uranium silicide (U 3Si 2) offer increased uranium density and enhanced thermophysical properties compared to conventional UO 2 fuel, while maintaining an acceptably high melting point. Enhancements to traditional UO 2 are also being considered that would increase the thermal conductivity of the fuel and fission product retention through various additives. However, some of these advanced fuels have very limited information available on their irradiation performance (microstructural evolution, swelling, fission gas release, etc.), particularly for the range of temperature and burnup that are relevant for LWR fuel pins. To address this issue, Oak Ridge National Laboratory has developed an experimental facility to irradiate miniature fuel specimens in the High Flux Isotope Reactor (HFIR). The small size of the fuel specimens simplifies the design, analysis, and post-irradiation evaluations. Post-irradiation examination will provide basic data on the stability and behavior of advanced fuels as a function of temperature and burnup. This report briefly summarizes the experiment facility designmore » concept and the assembly of the first set of experiments. The experiment contains six different types of UN-based fuel kernels UN TRISO particles with varying densities, impurity levels, and burnable absorber contents. The experiments were successfully assembled, welded, evaluated, and delivered to the HFIR along with a complete quality assurance fabrication package. Pictures of the assembly process are included in this report. The experiment is planned for insertion into the HFIR during cycle 480 (June 2018).« less

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
OSTI Identifier:
1458354
Report Number(s):
ORNL/SPR-2018/874
TRN: US1901654
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Petrie, Christian M., Burns, Joseph R., Morris, Robert Noel, Smith, Kurt R., Le Coq, Annabelle G., and Terrani, Kurt A. Irradiation of Miniature Fuel Specimens in the High Flux Isotope Reactor. United States: N. p., 2018. Web. doi:10.2172/1458354.
Petrie, Christian M., Burns, Joseph R., Morris, Robert Noel, Smith, Kurt R., Le Coq, Annabelle G., & Terrani, Kurt A. Irradiation of Miniature Fuel Specimens in the High Flux Isotope Reactor. United States. doi:10.2172/1458354.
Petrie, Christian M., Burns, Joseph R., Morris, Robert Noel, Smith, Kurt R., Le Coq, Annabelle G., and Terrani, Kurt A. Fri . "Irradiation of Miniature Fuel Specimens in the High Flux Isotope Reactor". United States. doi:10.2172/1458354. https://www.osti.gov/servlets/purl/1458354.
@article{osti_1458354,
title = {Irradiation of Miniature Fuel Specimens in the High Flux Isotope Reactor},
author = {Petrie, Christian M. and Burns, Joseph R. and Morris, Robert Noel and Smith, Kurt R. and Le Coq, Annabelle G. and Terrani, Kurt A.},
abstractNote = {The Advanced Fuels Campaign (AFC) within the US Department of Energy (DOE) Office of Nuclear Energy is considering several advanced ceramic fuels for use in light water reactors (LWRs) and/or advanced reactor concepts. Advanced fuels, such as uranium carbide (UC), uranium nitride (UN), and uranium silicide (U3Si2) offer increased uranium density and enhanced thermophysical properties compared to conventional UO2 fuel, while maintaining an acceptably high melting point. Enhancements to traditional UO2 are also being considered that would increase the thermal conductivity of the fuel and fission product retention through various additives. However, some of these advanced fuels have very limited information available on their irradiation performance (microstructural evolution, swelling, fission gas release, etc.), particularly for the range of temperature and burnup that are relevant for LWR fuel pins. To address this issue, Oak Ridge National Laboratory has developed an experimental facility to irradiate miniature fuel specimens in the High Flux Isotope Reactor (HFIR). The small size of the fuel specimens simplifies the design, analysis, and post-irradiation evaluations. Post-irradiation examination will provide basic data on the stability and behavior of advanced fuels as a function of temperature and burnup. This report briefly summarizes the experiment facility design concept and the assembly of the first set of experiments. The experiment contains six different types of UN-based fuel kernels UN TRISO particles with varying densities, impurity levels, and burnable absorber contents. The experiments were successfully assembled, welded, evaluated, and delivered to the HFIR along with a complete quality assurance fabrication package. Pictures of the assembly process are included in this report. The experiment is planned for insertion into the HFIR during cycle 480 (June 2018).},
doi = {10.2172/1458354},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {6}
}

Technical Report:

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