STRESS-STRAIN PROPERTIES OF IRRADIATED URANIUM-10 w/o MOLYBDENUM

Gates, J.E.; Bodine, E.G.; Bell, Jean C. Le; Bauer, A.A.; Calkins, G.D.

doi:10.2172/4312625

Cited by 9 publications

(9 citation statements)

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“…The average slope in MPa/% and standard deviation for each test temperature are 20°C, 884.21±13.15; 200-250°C, 417.63±16.81; 350°C, 422.25±14.75; 400-450°C, 320.43±17.88; and 550°C, 199.29±24.41. Room-temperature elastic-modulus values reported in the literature are in the low-to-mid 80s GPa range 8,9 -consistent with our roomtemperature test results.…”

Section: Slopesupporting

confidence: 92%

Elevated temperature tensile tests on DU–10Mo rolled foils

Schulthess

Lloyd

Rabin

et al. 2018

Journal of Nuclear Materials

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Section: Slopesupporting

confidence: 92%

Elevated temperature tensile tests on DU–10Mo rolled foils

Schulthess

Lloyd

Rabin

et al. 2018

Journal of Nuclear Materials

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“…The average slope in MPa/% and standard deviation for each test temperature are: 20°C: 884.21±13.15; 200-250°C: 417.63±16.81; 350°C: 422.25±14.75; 400-450°C: 320.43±17.88; 550°C: 199.29±24.41. Room-temperature elastic-modulus values reported in the literature are in the low-to-mid-80s GPa range 14,15 -consistent with our room-temperature test results.…”

Section: Slopesupporting

confidence: 91%

Elevated Temperature Tensile Tests on DU10Mo Rolled Foils TEV-2194 R1

Schulthess

2018

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Tensile mechanical properties for uranium-10 wt.% molybdenum (U-10Mo) foils are required to support modeling and qualification of new monolithic fuel plate designs. It is expected that depleted uranium-10 wt% Mo (DU-10Mo) mechanical behavior is representative of the low enriched U-10Mo to be used in the actual fuel plates, therefore DU-10Mo was studied to simplify material processing, handling, and testing requirements. In this report, tensile testing of DU-10Mo fuel foils prepared using four different thermomechanical processing treatments were conducted to assess the impact of foil fabrication history on resultant tensile properties.The Y-12 National Security Complex at Oak Ridge National Laboratory (Y12) provided Idaho National Laboratory (INL) with a cast and machined ~4.1 mm-thick, ~127 mm-wide, and ~182 mm-long plate of DU-10Mo. After receipt at INL, the plate (designated alloy 551) was sectioned into four pieces using wire electric discharge machining (wire EDM), and each piece was homogenized at 1000°C for two hours under vacuum of 5 x 10-6 Torr. These pieces were then individually hot-rolled into foil strips of varying thickness. Additional cold rolling was performed on three of the four foils to bring the final thickness of each cold rolled foil to a target of 0.38 mm, representative of the final thickness of actual fuel foils. The four foil conditions studied were as follows: Foil 551-2 -additional 50% cold-rolling reduction; Foil 551-3 -additional 50% coldrolling reduction followed by stress-relief annealing at 650°C for one hour; Foil 551-4 -additional 20% cold-rolling reduction; and Foil 551-5 -no further processing, i.e. hot-rolled only. Due to breach of the protective rolling can, hot rolling of foil 551-5 was terminated early, resulting in a final nominal thickness of 0.53 mm. Sub-size flat sheet-type tensile specimens, with dimensions scaled to 50% (i.e. 50 mm nominal overall length) of the normal subsize specimen, as specified in Figure 1 of ASTM E8/8M-13, were cut from the finished foil sheets using wire EDM machining. Tests were conducted on specimens with both longitudinal and transverse orientation relative to rolling direction, and at various temperatures between room temperature (per ASTM E8/8M-13) and elevated temperatures (per ASTM E21-10) up to 550°C. This work was conducted under PLN-4560, "GTRI Mechanical Property Characterization Test Plan," which contains additional requirements and instructions for testing. 1 The following report presents details of the testing system, testing methods, and mechanical properties determined from the test data.

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“…where we have used E = 70 GPa and = 0.33 for the aluminum and E = 86 GPa and = 0.35 for U-10Mo [27][28][29]. The indices can be cycled as necessary to solve for the remaining stress components.…”

Section: Residual Stressmentioning

confidence: 99%

Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates

Brown

Okuniewski

Sisneros

et al. 2016

Journal of Nuclear Materials

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Al clad U-10Mo fuel plates are being considered for conversion of several research reactors from high-enriched to low-enriched U fuel. Neutron diffraction measurements of the textures, residual phase stresses, and dislocation densities in the individual phases of the mini-foils throughout several processing steps and following hot-isostatic pressing to the Al cladding, have been completed. Recovery and recrystallization of the bare U-10Mo fuel foil, as indicated by the dislocation density and texture, are observed depending on the state of the material prior to annealing and the duration and temperature of the annealing process. In general, the cladding procedure significantly reduces the dislocation density, but the final state of the clad plate, both texture and dislocation density, depends strongly on the final processing step of the fuel foil. In contrast, the residual stress state of the final plate is dominated by the thermal expansion mismatch of the constituent materials.

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STRESS-STRAIN PROPERTIES OF IRRADIATED URANIUM-10 w/o MOLYBDENUM

Cited by 9 publications

References 0 publications

Elevated temperature tensile tests on DU–10Mo rolled foils

Elevated temperature tensile tests on DU–10Mo rolled foils

Elevated Temperature Tensile Tests on DU10Mo Rolled Foils TEV-2194 R1

Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates

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