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Title: Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations

Abstract

Several different U based metallic nuclear fuel alloys and forms were irradiated as part of the Advanced Fuels Campaign (AFC) series of irradiation experiments. Results from postirradiation examinations of the AFC-3A and AFC-3B are presented here. In this irradiation, U alloyed with Mo, Zr, and Zr with Pd were investigated. Different geometric forms (solid, annular), smear densities and bonding media (sodium, helium) were also irradiated and evaluated. All fuel forms were irradiated in ferritic-martensitic HT-9 cladding. Examination of the irradiated fuel included neutron radiography, evaluation of the distribution of gamma-ray emitting radionuclides, dimensional inspection, fission gas release analysis, optical microscopy, and chemical analysis. No in-pile failure was observed with this fuel. Neutron radiography, gamma spectrometry, and dimensional inspections indicated the fuel largely performed acceptably. Optical microscopy revealed significant fuel-cladding interaction between the Mo based alloys and the cladding. The Zr based alloys generally performed better although some forms revealed behaviors that present specific fabrication challenges such as tighter fabrication tolerances that will need to be better controlled to match historical U-Zr fuel performance. Furthermore, the addition of Pd as an additive to prevent fuel cladding chemical interaction (FCCI) also appears to present some challenges to fuel performance.

Authors:
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:
1484473
Alternate Identifier(s):
OSTI ID: 1548022
Report Number(s):
INL-JOU-18-50222-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; metallic fast reactor fuel; ultra-high burnup; additive; FCCI

Citation Formats

Harp, Jason M., Chichester, Heather J. M., and Capriotti, Luca. Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations. United States: N. p., 2018. Web. doi:10.1016/j.jnucmat.2018.07.003.
Harp, Jason M., Chichester, Heather J. M., & Capriotti, Luca. Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations. United States. doi:10.1016/j.jnucmat.2018.07.003.
Harp, Jason M., Chichester, Heather J. M., and Capriotti, Luca. Tue . "Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations". United States. doi:10.1016/j.jnucmat.2018.07.003. https://www.osti.gov/servlets/purl/1484473.
@article{osti_1484473,
title = {Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations},
author = {Harp, Jason M. and Chichester, Heather J. M. and Capriotti, Luca},
abstractNote = {Several different U based metallic nuclear fuel alloys and forms were irradiated as part of the Advanced Fuels Campaign (AFC) series of irradiation experiments. Results from postirradiation examinations of the AFC-3A and AFC-3B are presented here. In this irradiation, U alloyed with Mo, Zr, and Zr with Pd were investigated. Different geometric forms (solid, annular), smear densities and bonding media (sodium, helium) were also irradiated and evaluated. All fuel forms were irradiated in ferritic-martensitic HT-9 cladding. Examination of the irradiated fuel included neutron radiography, evaluation of the distribution of gamma-ray emitting radionuclides, dimensional inspection, fission gas release analysis, optical microscopy, and chemical analysis. No in-pile failure was observed with this fuel. Neutron radiography, gamma spectrometry, and dimensional inspections indicated the fuel largely performed acceptably. Optical microscopy revealed significant fuel-cladding interaction between the Mo based alloys and the cladding. The Zr based alloys generally performed better although some forms revealed behaviors that present specific fabrication challenges such as tighter fabrication tolerances that will need to be better controlled to match historical U-Zr fuel performance. Furthermore, the addition of Pd as an additive to prevent fuel cladding chemical interaction (FCCI) also appears to present some challenges to fuel performance.},
doi = {10.1016/j.jnucmat.2018.07.003},
journal = {Journal of Nuclear Materials},
number = C,
volume = 509,
place = {United States},
year = {2018},
month = {7}
}

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