The oxidation behavior of Zircaloy‐4 in steam between 600 and 1600°C

Leistikow, S.; Schanz, S. G.

doi:10.1002/maco.19850360302

Cited by 58 publications

(25 citation statements)

References 5 publications

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“…Belt polishing removes surface impurities in the range of 0.1-0.3 µm and may result in some additional cold working of the near-surface metal. In terms of hydrogen content or hydrogen pickup, the HBR-type Zry-4 (1980s) has a much higher breakaway-oxidation time (≈3800 s) than the time (≈1800 s) determined by Leistikow and Schanz [19,20] for 1970s Zry-4. The breakaway-oxidation time (≈5000 s) for modern AREVA 15×15 Zry-4 tested by ANL is comparable to the breakaway-oxidation time (≈5400 s) determined by Mardon et al [21] for modern AREVA 17×17 Zry-4.…”

Section: Breakaway Oxidation Time For 15×15 Zry-4 Samples Oxidized Atmentioning

confidence: 79%

“…Breakaway oxidation has been investigated by Leistikow and Schanz [19,20] for Zry-4 and Mardon et al [21] for Zry-4 and M5. Although the breakaway oxidation time is generally defined as the time corresponding to an increase in oxidation rate (i.e., weight gain rate), it is the associated hydrogen pickup that causes embrittlement.…”

Section: Breakaway Oxidation Time For 15×15 Zry-4 Samples Oxidized Atmentioning

confidence: 99%

“…Conversely, irregularities in surface geometry can result in alternating regions of compressive and tensile stresses. According to Leistikow and Schanz [19,20], such irregularities along the metal-oxide surface are a precursor to tetragonal-to-monoclinic transformation and breakaway oxidation.…”

Section: Effects Of Surface Conditions On Cladding Performancementioning

confidence: 99%

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Cladding embrittlement during postulated loss-of-coolant accidents.

Billone¹,

Yan²,

Burtseva³

et al. 2008

137

105

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The effect of fuel burnup on the embrittlement of various cladding alloys was examined with laboratory tests conducted under conditions relevant to loss-of-coolant accidents (LOCAs). The cladding materials tested were Zircaloy-4, Zircaloy-2, ZIRLO, M5, and E110. Tests were performed with specimens sectioned from as-fabricated cladding, from prehydrided (surrogate for high-burnup) cladding, and from high-burnup fuel rods which had been irradiated in commercial reactors. The tests were designed to determine for each cladding material the ductile-to-brittle transition as a function of steam oxidation temperature, weight gain due to oxidation, hydrogen content, pre-transient cladding thickness, and pre-transient corrosion-layer thickness. For short, defueled cladding specimens oxidized at 1000-1200ºC, ring compression tests were performed to determine post-quench ductility at ≤135ºC. The effect of breakaway oxidation on embrittlement was also examined for short specimens oxidized at 800-1000ºC. Among other findings, embrittlement was found to be sensitive to fabrication processes -especially surface finish -but insensitive to alloy constituents for these dilute zirconium alloys used as cladding materials. It was also demonstrated that burnup effects on embrittlement are largely due to hydrogen that is absorbed in the cladding during normal operation. Some tests were also performed with longer, fueledand-pressurized cladding segments subjected to LOCA-relevant heating and cooling rates. Recommendations are given for types of tests that would identify LOCA conditions under which embrittlement would occur. ForewordFuel rod cladding is the first barrier for retention of fission products, and the structural integrity of the cladding ensures coolable core geometry. In the early 1990s, new data from foreign research programs showed degraded cladding behavior for high-burnup fuel compared with low-burnup fuel in tests designed to simulate postulated accidents. Interim actions were taken, but it became clear that extrapolation from a low-burnup data base needed to be reassessed more carefully for regulatory purposes.One of NRC's central regulations used in plant licensing deals with postulated loss-of-coolant accidents (LOCAs). A portion of that regulation in 10 CFR 50.46(b) specifies criteria that were derived from tests with unirradiated Zircaloy cladding, and these criteria limit the peak cladding temperature and the maximum cladding oxidation during the accident. These two limits are known as embrittlement criteria. Their purpose is to prevent cladding embrittlement during a LOCA, thus ensuring that the general core geometry will be maintained and be coolable.In the mid-1990s, NRC sponsored a cooperative research program at Argonne National Laboratory to reassess these limits for the possible effects of fuel burnup. The program's industry partners included the Electric Power Research Institute, Framatome ANP (now AREVA), Westinghouse, and Global Nuclear Fuel; in general, the industry partners were responsible fo...

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Section: Breakaway Oxidation Time For 15×15 Zry-4 Samples Oxidized Atmentioning

confidence: 79%

Section: Breakaway Oxidation Time For 15×15 Zry-4 Samples Oxidized Atmentioning

confidence: 99%

See 1 more Smart Citation

Cladding embrittlement during postulated loss-of-coolant accidents.

Billone¹,

Yan²,

Burtseva³

et al. 2008

137

105

View full text Add to dashboard Cite

show abstract

“…The oxide thickness in the Arsteam mixture (steam partial pressure: 0.5 MPa) is quite close to that made at 1 atm steam. The solid line indicates the Leistikow's isothermal oxidation data of Zry-4 [6,7]. Based on this observation, it can be concluded that steam pressure is a more important factor affecting the high temperature oxidation of Zry-4 than is the total gas pressure.…”

Section: Resultsmentioning

confidence: 88%

“…The kinetics of Zircaloy oxidation in atmospheric steam below 1500 o C can be divided into two regions: the cubic rate law (below 950 o C) and the parabolic (above 1070 o C) [6]. Between 950 and 1070 o C, a mixed behavior of cubic and parabolic rates appears [7].…”

Section: Discussionmentioning

confidence: 99%

Pressure effects on high temperature steam oxidation of zircaloy-4

et al. 2001

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The pressure effects on the oxidation of Zircaloy-4 (Zry-4) cladding in high temperature steam have been analyzed. A double layer autoclave was made for the high pressure/high temperature oxidation tests. The experimental test temperature range was 700-900 o C, and pressures were 0.1-15 MPa. Steam partial pressure was found to be a more important factor than total pressure. Steam pressure enhances the oxidation rate of Zry-4 exponentially and depends on the temperature, the maximum being between 750-800 o C. A preexisting oxide layer decreases the enhancement by about 40-60%. The acceleration of the oxidation rate caused by high pressure steam seems to originate from the formation of cracks due to an abrupt transformation of the tetragonal phase in the oxide, where the instability of the tetragonal phase comes from the reduction of surface energy due to steam.

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Long‐Term High‐Temperature Oxidation of Al₁₀CoCrFeNi₃₀ High‐Entropy Alloy

Bastin,

Robertson,

Huang

et al. 2024

Adv Eng Mater

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The combined effects of high‐temperature and long‐term exposure to oxidation environment on an AlCoCrFeNi‐based high entropy alloy (HEA) are investigated. The alloy has a composition of Al10Co20Cr20Fe20Ni30 (at%) and is oxidized in lab air at 1000 °C for 1000 h to emulate working conditions and long operation cycles of gas turbines. The microstructure and oxide formation of the HEA are characterized using scanning electron microscopy, energy‐dispersive spectroscopy, and X‐ray diffraction. The performance of the HEA is compared to that of Inconel 625 and Hastelloy X and shows slower oxidation kinetics than Inconel 625 until 750 h. The HEA has the thinnest oxide layer of the three alloys and exhibits a triplex structure with a continuous Cr2O3 outer scale, a semi‐continuous Al2O3 subscale, and deep AlN precipitates. The matrix shows signs of Cr and Al depletion after 1000 h, leading to its inability to replace the degraded oxide scales that evaporated or spalled, and decreases its long‐term oxidation resistance. Overall, the HEA shows good oxidation resistance until 750 h, but may benefit from a higher Al content on the surface to form a longer‐lasting Al2O3 subscale that would remain protective beyond 750 h.

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The oxidation behavior of Zircaloy‐4 in steam between 600 and 1600°C

Cited by 58 publications

References 5 publications

Cladding embrittlement during postulated loss-of-coolant accidents.

Cladding embrittlement during postulated loss-of-coolant accidents.

Pressure effects on high temperature steam oxidation of zircaloy-4

Long‐Term High‐Temperature Oxidation of Al₁₀CoCrFeNi₃₀ High‐Entropy Alloy

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The oxidation behavior of Zircaloy‐4 in steam between 600 and 1600°C

Cited by 58 publications

References 5 publications

Cladding embrittlement during postulated loss-of-coolant accidents.

Cladding embrittlement during postulated loss-of-coolant accidents.

Pressure effects on high temperature steam oxidation of zircaloy-4

Long‐Term High‐Temperature Oxidation of Al10CoCrFeNi30 High‐Entropy Alloy

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Product

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Long‐Term High‐Temperature Oxidation of Al₁₀CoCrFeNi₃₀ High‐Entropy Alloy