Postirradiation examination on metallic fuel in the AFC-2 irradiation test series
Abstract
In this paper, irradiation experiments on metallic fuel alloys containing rare earth additions to simulate potential carry-over from pyro-metallurgical reprocessing and minor actinide additions were performed in the Idaho National Laboratory Advanced Test Reactor. These tests were designated AFC-2A and AFC-2B. Additionally irradiation experiments were also performed on metallic fuel alloys containing minor actinide additions that were fabricated by different techniques. These tests were designated AFC-2E. These pins were removed from the reactor after achieving burnups between 6 and 11% fission per initial heave metal atom. Examination of these pins revealed that they were unintentionally operated beyond their desired power and temperature conditions. Highlights from the postirradiation examination of these experiments is discussed. A variety of issue contributed to the poor performance of these irradiation tests including capsule design, reactor power variations and fabrication issues. While all the issues contributed, the major issue was determined to be unanticipated variations in reactor power. Through comparisons between these experiments and historical off-normal experiments, it was possible to conclude bound the operating temperatures of these experiments. There likely was some in-pile melting in the rare earth addition experiments (AFC-2A, AFC-2B), but it is not likely that there was in-pile melting in the fabricationmore »
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1484472
- Alternate Identifier(s):
- OSTI ID: 1495279
- Report Number(s):
- INL-JOU-18-50163-Rev000
Journal ID: ISSN 0022-3115
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 509; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AFC-2; postirradiation examination; metallic fast reactor fuel; lanthanide carry-over; ternary fuel
Citation Formats
Harp, Jason M., Capriotti, Luca, Chichester, Heather J. M., Medvedev, Pavel G., Porter, Douglas L., and Hayes, Steven L. Postirradiation examination on metallic fuel in the AFC-2 irradiation test series. United States: N. p., 2018.
Web. doi:10.1016/j.jnucmat.2018.07.019.
Harp, Jason M., Capriotti, Luca, Chichester, Heather J. M., Medvedev, Pavel G., Porter, Douglas L., & Hayes, Steven L. Postirradiation examination on metallic fuel in the AFC-2 irradiation test series. United States. https://doi.org/10.1016/j.jnucmat.2018.07.019
Harp, Jason M., Capriotti, Luca, Chichester, Heather J. M., Medvedev, Pavel G., Porter, Douglas L., and Hayes, Steven L. Wed .
"Postirradiation examination on metallic fuel in the AFC-2 irradiation test series". United States. https://doi.org/10.1016/j.jnucmat.2018.07.019. https://www.osti.gov/servlets/purl/1484472.
@article{osti_1484472,
title = {Postirradiation examination on metallic fuel in the AFC-2 irradiation test series},
author = {Harp, Jason M. and Capriotti, Luca and Chichester, Heather J. M. and Medvedev, Pavel G. and Porter, Douglas L. and Hayes, Steven L.},
abstractNote = {In this paper, irradiation experiments on metallic fuel alloys containing rare earth additions to simulate potential carry-over from pyro-metallurgical reprocessing and minor actinide additions were performed in the Idaho National Laboratory Advanced Test Reactor. These tests were designated AFC-2A and AFC-2B. Additionally irradiation experiments were also performed on metallic fuel alloys containing minor actinide additions that were fabricated by different techniques. These tests were designated AFC-2E. These pins were removed from the reactor after achieving burnups between 6 and 11% fission per initial heave metal atom. Examination of these pins revealed that they were unintentionally operated beyond their desired power and temperature conditions. Highlights from the postirradiation examination of these experiments is discussed. A variety of issue contributed to the poor performance of these irradiation tests including capsule design, reactor power variations and fabrication issues. While all the issues contributed, the major issue was determined to be unanticipated variations in reactor power. Through comparisons between these experiments and historical off-normal experiments, it was possible to conclude bound the operating temperatures of these experiments. There likely was some in-pile melting in the rare earth addition experiments (AFC-2A, AFC-2B), but it is not likely that there was in-pile melting in the fabrication technique experiments (AFC-2E).},
doi = {10.1016/j.jnucmat.2018.07.019},
journal = {Journal of Nuclear Materials},
number = C,
volume = 509,
place = {United States},
year = {Wed Jul 11 00:00:00 EDT 2018},
month = {Wed Jul 11 00:00:00 EDT 2018}
}
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Works referencing / citing this record:
Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons
journal, November 2019
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