Four-point Bend Testing of Irradiated Monolithic U-10Mo Fuel

Conference · Sun Mar 01 04:00:00 EST 2015

OSTI ID:1177230

Rabin, B. H. ^[1]; Lloyd, W. R. ^[1]; Schulthess, J. L. ^[1]; Wright, J. K. ^[1]; Lind, R. P. ^[1]; Scott, L. ^[1]; Wachs, K. M. ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

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.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1177230
• Report Number(s): INL/CON--14-33660
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
BENDING
BINARY ALLOY SYSTEMS
DIAGRAMS
FRACTURE PROPERTIES
FUEL PLATES
IRRADIATION
MOLYBDENUM ALLOYS
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
STRAINS
STRESSES
TESTING
URANIUM BASE ALLOYS
mechanical properties
nuclear fuel
uranium-molybdenum alloys