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

Journal Article · · Journal of Nuclear Materials
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.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1484473
Alternate ID(s):
OSTI ID: 1548022
OSTI ID: 22752192
Report Number(s):
INL-JOU--18-50222-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 509; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (27)

Swelling behavior of U-Pu-Zr fuel journal February 1990
Irradiation behavior of metallic fast reactor fuels journal June 1992
History of fast reactor fuel development journal September 1993
Experience with advanced driver fuels in EBR-II journal September 1993
Temperature gradient driven constituent redistribution in UZr alloys journal January 1996
Metallic fast reactor fuels journal January 1997
Fuels for sodium-cooled fast reactors: US perspective journal September 2007
A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design journal June 2009
Metallic fuels for advanced reactors journal July 2009
Migration of minor actinides and lanthanides in fast reactor metallic fuel journal July 2009
Interdiffusion and reaction between uranium and iron journal May 2012
Full-length U–xPu–10Zr (x=0, 8, 19wt.%) fast reactor fuel test in FFTF journal August 2012
U–Mo alloy fuel for TRU-burning advanced fast reactors journal October 2013
Reduction of FCCI effects in lanthanide–iron diffusion couples by doping with palladium journal September 2013
Performance of low smeared density sodium-cooled fast reactor metal fuel journal October 2015
Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9 journal October 2017
SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln journal October 2017
Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides journal January 2018
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data journal December 2011
An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques journal October 2014
Testing fast reactor fuels in a thermal reactor journal March 2018
Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory journal January 2015
ATR Compendium: Irradiation Test Capabilities journal January 2018
Hardening neutron spectrum for advanced actinide transmutation experiments in the ATR journal December 2005
Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel journal January 1980
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors journal May 1984
Development of Electrorefiner Waste salt Disposal Process for the ebr- ii Spent fuel Treatment Project journal April 2008

Cited By (1)

Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons journal November 2019

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