Actions for Four-point Bend Testing of Irradiated Monolithic U-10Mo Fuel [electronic resource].

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Four-point Bend Testing of Irradiated Monolithic U-10Mo Fuel [electronic resource].

Published
Washington, D.C. : United States. National Nuclear Security Administration, 2015.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description
18 pages : digital, PDF file
Additional Creators
Idaho National Laboratory, United States. National Nuclear Security Administration, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
This paper presents results of recently completed studies aimed at characterizing the mechanical properties of irradiated U-10Mo fuel in support of monolithic base fuel qualification. Mechanical properties were evaluated in four-point bending. Specimens were taken from fuel plates irradiated in the RERTR-12 and AFIP-6 Mk. II irradiation campaigns, and tests were conducted in the Hot Fuel Examination Facility (HFEF) at Idaho National Laboratory (INL). The monolithic fuel plates consist of a U-10Mo fuel meat covered with a Zr diffusion barrier layer fabricated by co-rolling, clad in 6061 Al using a hot isostatic press (HIP) bonding process. Specimens exhibited nominal (fresh) fuel meat thickness ranging from 0.25 mm to 0.64 mm, and fuel plate average burnup ranged from approximately 0.4 x 1021 fissions/cm3 to 6.0 x 1021 fissions/cm3. After sectioning the fuel plates, the 6061 Al cladding was removed by dissolution in concentrated NaOH. Pre- and post-dissolution dimensional inspections were conducted on test specimens to facilitate accurate analysis of bend test results. Four-point bend testing was conducted on the HFEF Remote Load Frame at a crosshead speed of 0.1 mm/min using custom-designed test fixtures and calibrated load cells. All specimens exhibited substantially linear elastic behavior and failed in a brittle manner. The influence of burnup on the observed slope of the stress-strain curve and the calculated fracture strength is discussed.
Report Numbers
E 1.99:inl/con--14-33660
inl/con--14-33660
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Note
Published through SciTech Connect.
03/01/2015.
"inl/con--14-33660"
2015 Research Reactor Fuel Management Conference (RRFM 2015), Bucharest (Romania), 19-23 Apr 2015.
Rabin, B. H. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Lloyd, W. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Schulthess, J. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Wright, J. K. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Lind, R. P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Scott, L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)]; Wachs, K. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)].
Funding Information
AC07-05ID14517
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