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Title: 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 » technique experiments (AFC-2E).« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
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. doi: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. doi: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 = {2018},
month = {7}
}

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