FY21 burst activities with coated Zircaloy-4 under accident conditions

Garrison, Ben; Linton, Kory; Kane, Kenneth; Hawkins, Charles; Bell, Samuel; Johnston, B G.; Gräning, Tim; Nelson, Andrew T.

doi:10.2172/1818671

Cited by 6 publications

(5 citation statements)

References 25 publications

(49 reference statements)

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“…The geometry and chemical composition of Zircaloy-4 tubes are shown in Table 1. As shown in recent reports [15,16] the surface finish of Zry-4 tubes was not smooth enough for direct coating on the surface of as-received material. Adhesion of the coating was not sufficient, and the directional growth of the coating during the HiPIMS process led to cracks and uncoated areas.…”

Section: Zircaloy-4 Cladding Materialsmentioning

confidence: 85%

“…Previously, testing was conducted on 305 mm lengths of Zry-4 coated with a "poor" quality Cr coating that possessed interfacial and through-coating cracking resultant of a poor surface finish prior to deposition (Figure 3), along as 305 mm lengths of bare Zry-4 [15]. Although limited testing was performed, no improvement in burst strength, which manifests as higher burst temperatures at similar hoop stresses, was observed, Figure 11.…”

Section: Burst Test Resultsmentioning

confidence: 99%

“…The selected temperature was about 190 to 210 °C. To increase the adhesion in comparison with the coating presented in a recent report [15], a substrate bias of around -1000 V was applied during the initial 10 minutes of the coating process. After that initial step, the substrate voltage bias was set to -100, -150, and -200 V for seven tubes each.…”

Section: Coating Fabricationmentioning

confidence: 99%

“…HiPIMS PVD coating growth occurs very directional and mirrors the substrate surface [17]. Figure 3 shows the impact of a bad adhesion of a coating applied with a low substrate voltage bias of -35V on a tube with a high local peak roughness value [15]. Although this effort was ultimately unsuccessful in obtaining a continuous coating, it did supply material where a high fraction of the surface was coated with discrete defective points.…”

Section: Coating Fabricationmentioning

confidence: 99%

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Impact of Coating Defects on Performance of Coated Zirconium Cladding

Seibert¹,

Kane²,

Garrison³

et al. 2021

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The Advanced Fuels Campaign has made progress in developing an ability to fabricate high quality 'generic' chromium coatings applied to commercial nuclear cladding alloys free of the proprietary considerations inherent to the industry materials. The availability of such source material is critical for execution of fundamental studies as well as open collaboration between the national laboratories, within Office of Nuclear Energy programs, and the Nuclear Regulatory Commission. This milestone report provides insights on the impact of processing parameters on the microstructure of 7 micron Cr-coated Zircaloy-4. Coatings were applied using High Power Impulse Magnetron Sputtering (HiPIMS). Scanning electron microscopy was utilized to investigate the overcoating of cladding and cross-sections of the interface. Characterization confirmed that a high quality, continuous coating was achieved. Burst testing was then performed to evaluate the performance of high-quality coatings to coatings that contain known flaws and uncoated materials. Results demonstrated that coatings containing flaws allowing for direct exposure of the base cladding to atmosphere exhibit burst behavior matching that of the uncoated material. However, continuous coatings resulted in measurable improvement. This work will be expanded in FY22 to include a broader set of mechanical property studies and test irradiations.

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Section: Zircaloy-4 Cladding Materialsmentioning

confidence: 85%

Section: Burst Test Resultsmentioning

confidence: 99%

Section: Coating Fabricationmentioning

confidence: 99%

Section: Coating Fabricationmentioning

confidence: 99%

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Impact of Coating Defects on Performance of Coated Zirconium Cladding

Seibert¹,

Kane²,

Garrison³

et al. 2021

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“…As a result, select tests were also performed with hand-polished uncoated tubes as well. More information on the Zircaloy-4 material can be found in Garrison et al [21], and the coating methodologies can be found in Graening et al [20]. Tests were performed at room temperature and at 300°C on an Instron 5966 electromechanical test system or on an MTS electromechanical system, based on system availability.…”

Section: Materials and Testingmentioning

confidence: 99%

Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database

Garrison,

Massey,

Ren

et al. 2023

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To support a multi-laboratory Methodology, Evaluation, Testing, and Analysis (M.E.T.A.) cladding properties database, Oak Ridge National Laboratory's (ORNL's) cladding mechanical test geometries were manufactured from several nuclear-relevant cladding alloys and subsequently tested. These geometries were developed as mechanical test specimens to evaluate the properties of tube materials that may be used for irradiation testing at ORNL's High Flux Isotope Reactor. They may also be used as test articles to be harvested-via in-cell machining-from commercially irradiated fuel rods and later tested. This report explores the differences among axial, hoop, and SSJ tensile geometries with partially recrystallized Zircaloy-2 to test ORNL correlation-based methods on a plate material that approximates, to the greatest extent possible, the characteristics of nuclear industry tubing. Furthermore, several tests were conducted with ORNL's Zircaloy-4 tube inventory to (1) develop material properties as a standard for future tests, (2) determine the effect of the US Department of Energy's Advanced Fuels Campaign coating processes on tube mechanical properties, and (3) evaluate the effect of specimen machining methods on the mechanical properties of tube geometries.

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