Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing

Bell, Samuel; Gräning, Tim; Kelly, Peter; Pint, Bruce A.; Kane, Kenneth

doi:10.1016/j.jnucmat.2022.153679

Cited by 7 publications

(5 citation statements)

References 46 publications

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“…To predict the balloon-burst behavior, Z. Ma et al (2021b) perform numerical simulations using ABAQUS software. They conclude that thicker coatings may slightly increase the burst strain rate, but overall, the effect of coating thickness on balloon and burst temperature is not significant, which somewhat contradicts the experimental results of Bell et al (2022). Since the thickness data of the coating samples cited by Ma et al and shown in Figure 10 "General results" are greater than 10 μm, it is likely that the change in burst size will show a deviated trend for thinner coatings.…”

Section: Balloon and Burst Behaviormentioning

confidence: 90%

“…basically the same at high pressure, but the burst temperature of the Cr-coated sample is lower at low pressure level, and no significant effect of the coating on radial strain is found. The oxidation on the opposite side of the burst opening proves that the Cr coating has General results of general cladding balloon and burst tests (Park et al, 2016;Brachet et al, 2017;Dumerval et al, n.d.) and the abnormal results (Bell et al, 2022).…”

Section: Balloon and Burst Behaviormentioning

confidence: 97%

“…Interestingly, Bell et al (2022) perform EDS observations in the rupture area where the Cr-coated samples undergo large internal pressure. It is found that under Cr 2 O 3 layer, the Cr layer remained is discontinuous.…”

Section: High-temperature Oxidation Behaviormentioning

confidence: 99%

“…FIGURE 10General results of general cladding balloon and burst tests(Park et al, 2016;Brachet et al, 2017; Dumerval et al, n.d.) and the abnormal results(Bell et al, 2022).…”

mentioning

confidence: 98%

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Review on performance of chromium-coated zirconium and its failure mechanisms

Li,

Wang,

Chen

et al. 2023

Front. Nucl. Eng.

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The conventional Zircaloy cladding may react with coolant in light water reactors and elicit severe accident at high temperature, which constraint the safe and efficient development of nuclear energy. To avoid the tragedy happened in Fukushima, the concept of Accident Tolerant Fuel (ATF) was developed around the globe to secure the steady operation for nuclear power plants. As a short-term solution, deposition of protective coatings upon the cladding tubes are proved to be effective. Among the coatings, Chromium is one of the most outstanding choices. This paper reviews the recent study results about the performance and failure mechanisms of Cr-coated Zr cladding, including mechanical, irradiation, high-temperature oxidation tests, etc. under normal and/or accident conditions. The experiments and tests collectively suggest that Cr coating possesses excellent comprehensive properties for integrity protection of claddings and provides a promising future of the commercial application in reactor cores. Finally, this review proposes ambiguities and questions needed to be analyzed and clarified in future works.

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Section: Balloon and Burst Behaviormentioning

confidence: 90%

Section: Balloon and Burst Behaviormentioning

confidence: 97%

Section: High-temperature Oxidation Behaviormentioning

confidence: 99%

“…FIGURE 10General results of general cladding balloon and burst tests(Park et al, 2016;Brachet et al, 2017; Dumerval et al, n.d.) and the abnormal results(Bell et al, 2022).…”

mentioning

confidence: 98%

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Review on performance of chromium-coated zirconium and its failure mechanisms

Li,

Wang,

Chen

et al. 2023

Front. Nucl. Eng.

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“…This scenario would leave the cladding material as the underlying Zr alloy, which is presumably already licensed [5]. Even though many methods have been developed to investigate coatings for cladding materials and their mechanical properties [6,7], including the oxidation resistance of Cr coatings [8][9][10][11][12][13], a general understanding of hydriding behavior of Cr-coated cladding is missing. In this work, Cr-coated claddings and bare cladding were compared by hydriding them to different target hydrogen levels.…”

Section: Introductionmentioning

confidence: 99%

Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing

Yan

Graening

Nelson

2022

Metals

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Accident-tolerant fuel concepts have been developed recently in diverse research programs. Recent research has shown clear advantages of Cr-coated Zr cladding over bare cladding tubes regarding oxidation behavior under the design basis loss-of-coolant accident condition. However, limited data are available about the hydriding behavior of the Cr coating. For that purpose, Cr-coated Zricaloy-4 tubes were tested to investigate the effects of hydriding, oxidation, and postquench ductility behavior on coated Zr cladding. A high-power impulse magnetron sputtering (HiPIMS) process was used to produce a high-density coating on the Zircaloy-4 tube surface. Coated and uncoated Zircaloy-4 tube specimens underwent one-sided hydriding in a tube furnace filled with pure hydrogen gas at 425 °C. The tubing specimen ends were sealed with Swagelok plugs before the hydriding runs. For uncoated specimens, H analysis of the hydrided specimens indicated that the H content increased as the test time and initial pressure increased. However, almost no change was observed for the coated specimens that were hydrided under the same test conditions. After one-sided hydriding, the hydrided coated and uncoated specimens were exposed to steam at high temperatures for two-sided oxidation studies to simulate accident conditions. The coated specimens showed a slower oxidation: oxygen pickup was 50% lower than the uncoated specimens tested under the same conditions. Ring compression testing was performed to evaluate the embrittlement behavior of the Cr-coated specimens after hydriding and oxidation. The results indicated that the HiPIMS coating provides excellent protection from hydriding and oxidation at high temperatures.

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