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Original Article Microstructural characterization of accident tolerant fuel cladding with CreAl alloy coating layer after oxidation at 1200 C in a steam environment Dong Jun Park * , Yang Il Jung, Jung Hwan Park, Young Ho Lee, Byoung Kwon Choi, Hyun Gil Kim Korea Atomic Energy Research Institute,111 Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea article info Article history: Received 12 February 2020 Received in revised form 11 March 2020 Accepted 7 April 2020 Available online 11 April 2020 Keywords: Accident tolerant fuel CreAl alloy Zr alloy Coating High temperature oxidation Microstructure abstract Zr alloy specimens were coated with CreAl alloy to enhance their resistance to oxidation. The coated samples were oxidized at 1200 C in a steam environment for 300 s and showed extremely low oxidation when compared to uncoated Zr alloy specimens. The microstructure and elemental distribution of the oxides formed on the surface of CreAl alloys have been investigated by transmission electron microscopy (TEM) and X-ray photoelectron spectroscopy (XPS). A very thin protective layer of Cr 2 O 3 formed on the outer surface of the CreAl alloy, and a thin Al 2 O 3 layer was also observed in the CreAl alloy matrix, near the surface. Our results suggest that these two oxide layers near the surface confers excellent oxidation resistance to the CreAl alloy. Even after exposure to a high temperature of 1200 C, inter-diffusion be- tween the CreAl alloy and the Zr alloy occurred in very few regions near the interface. Analysis of the inter-diffusion layer by high-resolution transmission electron microscopy (HRTEM) and energy disper- sive X-ray spectroscopy (EDS) measurement conrmed its identity as Cr 2 Zr. © 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/). 1. Introduction Loss-of-coolant accident (LOCA) is one of several design basis accidents that can occur in a light water reactor. In the event of a LOCA, the Zr-based alloy used for the nuclear fuel cladding, and the core components are subjected to very high temperatures above 1000 C in an environment containing water vapor. This leads to substantial oxidation of the Zr alloy. The hydrogen generated as a by-product of the Zr-water reaction may result in an explosion [1 ,2], under certain conditions, as in the case of the Fukushima nuclear power plant [3]. Many studies have been devoted to developing an accident tolerant fuel (ATF) cladding, that can maintain its integrity for an extended period, in the event of an accident. One approach is to coat the existing Zr alloy cladding with oxidation-resistant high- temperature materials. In our previous research, we developed a CreAl alloy as a coating material, after consideration and screening of various materials as potential options [4]. For almost one hundred years, researchers have undertaken extensive studies of the binary AleCr system. However, most of those studies focused on various complex intermediate phases in the Al-rich region (up to 40 at. % Cr), such as Al 7 Cr, Al 11 Cr 2 ,A l4 Cr, Al 9 Cr 4 , Al 8 Cr 5 , and AlCr 2 [5e11]. As the Cr content of those intermediate phases increases, the melting temperature also increases, but they are still not suit- able for use as high-temperature materials above 1000 C. There- fore, Cr-rich solid solution alloys with a Cr content of 70 wt% or more are considered as suitable high-temperature materials since the melting temperature of these alloys is usually over 1600 C[6]. Additionally, Al-rich AleCr alloys readily undergo phase changes, even with a small change in composition. The microstructure is also difcult to control during alloy manufacturing. On the other hand, the Cr-based CreAl solid solution alloys are relatively easy to manufacture, and their microstructure is more easily controlled during the manufacturing process. In a previous study performed at this laboratory, CreAl alloy demonstrated excellent performance under extreme conditions of high temperature and exposure to a steam environment when compared to pure Cr [12]. However, a detailed mechanism for the oxidation of the CreAl alloy has not been systematically investigated, and a microstructural analysis has not been undertaken. * Corresponding author. E-mail address: [email protected] (D.J. Park). Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net https://doi.org/10.1016/j.net.2020.04.005 1738-5733/© 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/ licenses/by-nc-nd/4.0/). Nuclear Engineering and Technology 52 (2020) 2299e2305

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lable at ScienceDirect

Nuclear Engineering and Technology 52 (2020) 2299e2305

Contents lists avai

Nuclear Engineering and Technology

journal homepage: www.elsevier .com/locate/net

Original Article

Microstructural characterization of accident tolerant fuel claddingwith CreAl alloy coating layer after oxidation at 1200 �C in a steamenvironment

Dong Jun Park*, Yang Il Jung, Jung Hwan Park, Young Ho Lee, Byoung Kwon Choi,Hyun Gil KimKorea Atomic Energy Research Institute, 111 Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea

a r t i c l e i n f o

Article history:Received 12 February 2020Received in revised form11 March 2020Accepted 7 April 2020Available online 11 April 2020

Keywords:Accident tolerant fuelCreAl alloyZr alloyCoatingHigh temperature oxidationMicrostructure

* Corresponding author.E-mail address: [email protected] (D.J. Park).

https://doi.org/10.1016/j.net.2020.04.0051738-5733/© 2020 Korean Nuclear Society, Publishedlicenses/by-nc-nd/4.0/).

a b s t r a c t

Zr alloy specimens were coated with CreAl alloy to enhance their resistance to oxidation. The coatedsamples were oxidized at 1200 �C in a steam environment for 300 s and showed extremely low oxidationwhen compared to uncoated Zr alloy specimens. The microstructure and elemental distribution of theoxides formed on the surface of CreAl alloys have been investigated by transmission electron microscopy(TEM) and X-ray photoelectron spectroscopy (XPS). A very thin protective layer of Cr2O3 formed on theouter surface of the CreAl alloy, and a thin Al2O3 layer was also observed in the CreAl alloy matrix, nearthe surface. Our results suggest that these two oxide layers near the surface confers excellent oxidationresistance to the CreAl alloy. Even after exposure to a high temperature of 1200 �C, inter-diffusion be-tween the CreAl alloy and the Zr alloy occurred in very few regions near the interface. Analysis of theinter-diffusion layer by high-resolution transmission electron microscopy (HRTEM) and energy disper-sive X-ray spectroscopy (EDS) measurement confirmed its identity as Cr2Zr.© 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the

CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

1. Introduction

Loss-of-coolant accident (LOCA) is one of several design basisaccidents that can occur in a light water reactor. In the event of aLOCA, the Zr-based alloy used for the nuclear fuel cladding, and thecore components are subjected to very high temperatures above1000 �C in an environment containing water vapor. This leads tosubstantial oxidation of the Zr alloy. The hydrogen generated as aby-product of the Zr-water reactionmay result in an explosion [1,2],under certain conditions, as in the case of the Fukushima nuclearpower plant [3].

Many studies have been devoted to developing an accidenttolerant fuel (ATF) cladding, that can maintain its integrity for anextended period, in the event of an accident. One approach is tocoat the existing Zr alloy cladding with oxidation-resistant high-temperature materials. In our previous research, we developed aCreAl alloy as a coating material, after consideration and screeningof various materials as potential options [4]. For almost one

by Elsevier Korea LLC. This is an

hundred years, researchers have undertaken extensive studies ofthe binary AleCr system. However, most of those studies focusedon various complex intermediate phases in the Al-rich region (up to40 at. % Cr), such as Al7Cr, Al11Cr2, Al4Cr, Al9Cr4, Al8Cr5, and AlCr2[5e11]. As the Cr content of those intermediate phases increases,the melting temperature also increases, but they are still not suit-able for use as high-temperature materials above 1000 �C. There-fore, Cr-rich solid solution alloys with a Cr content of 70 wt% ormore are considered as suitable high-temperature materials sincethe melting temperature of these alloys is usually over 1600 �C [6].Additionally, Al-rich AleCr alloys readily undergo phase changes,evenwith a small change in composition. Themicrostructure is alsodifficult to control during alloy manufacturing. On the other hand,the Cr-based CreAl solid solution alloys are relatively easy tomanufacture, and their microstructure is more easily controlledduring themanufacturing process. In a previous study performed atthis laboratory, CreAl alloy demonstrated excellent performanceunder extreme conditions of high temperature and exposure to asteam environment when compared to pure Cr [12]. However, adetailed mechanism for the oxidation of the CreAl alloy has notbeen systematically investigated, and amicrostructural analysis hasnot been undertaken.

open access article under the CC BY-NC-ND license (http://creativecommons.org/

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D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e23052300

In this study, we used a Cr-10 wt% Al alloy to coat the Zr-basedalloy to improve its temperature resistance during LOCA scenarios.Zr-based alloy samples coated with a CreAl layer were exposed to atemperature of 1200 �C in a steam environment. Uncoated Zr-basedalloy was also exposed to the same test conditions to compare theefficacy of the coating layer. The microstructure and elementaldistribution of the oxides formed on the surface of the CreAl alloy,the CreAl alloy matrix, and the interfacial region between thecoated CreAl alloy and Zr-based alloywere analyzed in detail, usingfield emission transmission electron microscopy (FETEM). X-rayphotoelectron spectroscopy (XPS) was also used to confirm theexact elemental composition, chemical state, and electronic state ofthe elements in the oxides formed on the CreAl alloy. These resultscoincidedwith the high-resolution TEM (HRTEM) results. We foundthat depending on the distance from the surface, different oxides ofCr2O3 and Al2O3 were formed in the CreAl layer. It was expectedthat these protective and stable oxides near the surface of the CreAllayer would result in superior high-temperature oxidation resis-tance of the CreAl alloys.

2. Materials and methods

A cathodic arc ion plating (AIP) technique was used to form theCr-based CreAl alloy layer on the surface of Zr alloy samples. AIP isa high energy deposition process that employs a vacuum arc togenerate ionized vapor from target materials [13]. Before coating,the surfaces of all Zr alloy specimens were ultrasonically cleaned indeionized water, acetone, and alcohol to remove any organic sub-stances. Rotary and turbomolecular pumps were used to evacuatethe deposition chamber, and the base pressure was approximatelyless than 1 � 10�5 Torr. Prior to the deposition phase, the substratewas heated to 200 �C to remove humidity. The surface of the sub-stratewas then sputtered to clean and remove contaminants and tofacilitate better adhesion between the coating layer and the sub-strate. The arc current and the substrate bias voltage during theCreAl alloy layer deposition were 80 A and �200 V, respectively.High purity Ar gas (99.999%) was introduced into the depositionchamber to maintain the working pressure at 20 mTorr. The pres-sure of the Ar gas at the inlet was kept at 1 � 10�2 Torr during thedeposition phase. The composition of the coated layer was deter-mined to be Cr-based CreAl alloy containing 10 wt% of Al. Thisoptimum content of Al was determined through various test per-formed in our previous work [12].

In order to compare the high-temperature oxidation behavior ofthe coated and uncoated Zr alloy samples under LOCA scenarioconditions, the specimens were exposed to a flow of water vapor athigh temperature, using an infra-red radiation furnace. The sam-ples were enclosed in a vertical quartz tube for steam flow and awater quench. The furnace was then heated to a pre-test holdingtemperature of 300 �C for 240 s, whereas pure steam flow andsample temperature were stabilized for 500 s. The steam wassupplied with a flow rate of 5 mg/cm2/s. A heating rate of 28 �C/sfrom 300 �C to 1000 �C and 2.5 �C/s from 1000 �C to 1200 �C wereused. After exposure at 1200 �C for 300 s in the steam environment,the sample was slowly cooled to 800 �C and then quenched byflooding with water from the base. Further details of the testequipment and experimental procedures can be found in our pre-vious paper [14].

After oxidation, the samples were analyzed using conventionaloptical microscopy (OM), FETEM (JEM-2100F, JEOL, Japan) coupledwith energy dispersive spectroscopy (EDS, INCA, Oxford, UnitedKingdom), and XPS (Sigma Probe, VG/Thermo Fisher Scientific,Waltham, MA, USA). Foils for TEM analysis was prepared using afocused ion beam/SEM system (Quant™ 3D FEG, FEI, America).Digital image processing, such as fast Fourier transform (FFT) and

inverse FFT, using HRTEM images were performed with aid ofanalysis software (Digital Micrograph, Gatan). National Center forElectron Microscopy Simulation Software (NCEMSS, LawrenceBerkeley National Laboratory in Berkeley, California, USA) was alsoused to compare the experimental atomic arrangement with thesimulated result. Peaks obtained from the XPS analysis were fittedby OriginPro7.5 (OriginLab Corporation, Northampton, MA, USA).

3. Results and discussion

CreAl alloy-coated and uncoated Zr samples were exposed tothe 1200 �C steam environment for 300 s. After oxidation, all thesamples were cut, polished, and etched for OM analysis. Fig. 1shows their cross-sectional metallographs obtained from OM. Asshown in Fig. 1(b), ZrO2, and oxygen-stabilized a-Zr(O) layers wereformed due to oxygen diffusion during high-temperature steamexposure. In contrast, the CreAl alloy-coated (~20 mm) Zr samplesshowed no significant oxidation at the outer surface and oxygen-stabilized a-Zr(O) layer in the Zr matrix, despite the same testconditions as the uncoated sample. In addition, the coated CreAlalloy layer remained tightly bonded to the matrix without exhib-iting coating spallation and/or formation of defects such as cracksand pores. These results indicate that the Zr matrix can beadequately protected from 1200 �C steam exposure due to thecoated CreAl alloy layer, which produces an improved high-temperature oxidation resistance.

TEManalysiswasperformedon the oxidizedCreAl alloy coatedZrsample at 1200 �C. Fig. 2 shows the cross-sectional bright-field anddark-field images corresponding to theweak diffraction spot near theinterface between the coated CreAl alloy layer and the Zrmatrix. Theinterfaces are shown by white dotted lines in Fig. 2(a) and (b). TheseTEM images indicate that the columnar structure of the coated layernear the interface was maintained even after exposure to the high-temperature steam environment. The actual size and location of theaperture are shown by the white dotted circles, and correspondingselected area diffraction (SAD) patterns are shown as an inset in eachfigure.Basedontheratioof thespot spacingandanglesbetweenspotsin the SAD patterns, both regions are determined to reflect thediffraction patterns of the crystalline body-centered cubic (BCC) Cr([113] and [001] zone axis (ZA)). All SAD patterns show very sharpspots without the superposition of spots from any other crystallinestructure. This indicates that the same crystalline structure wasmaintained in each CreAl columnar grain. Some cracks or holes areobserved in the TEM images, thought to result from damage causedduring the preparation of the foil for TEM analysis.

HRTEM observations were carried out to precisely determinethe crystal structure of the CreAl alloy layer near the interface, andthe HRTEM image of CreAl is shown in Fig. 3(a). The HRTEM imageshowed a single crystalline atomic arrangement. The Fast Fouriertransform (FFT) pattern of the region in Fig. 3(a) is shown inFig. 3(b). Streaking lines in FFT patterns are artifacts generated dueto the intensity mismatch at the image edge. Distances and anglesbetween individual spots in the FFT pattern were quantified fortheir indexing. We concluded that the analyzed structure is anatomic arrangement of BCC Cr along the [111] zone axis.

The more detailed microstructure and elemental distributionnear the interfacial region were investigated using scanning TEM(STEM), and EDS analysis, as shown in Fig. 4. Fig. 4(a) represents thebright-field STEM image of the interfacial region, where the threeclearly distinguished regions, indicated by white dotted lines, areobserved. The elemental distribution maps from EDS analysis inFig. 4(c) and (d) show the upper CreAl alloy coating layer, themiddle region formed by inter-diffusion of Cr and Zr, and the lowerZr matrix. The width of the diffusion layer is about 1.145 mm, andcontains both Cr and Zr elements. To identify the phase and

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Fig. 1. OM images of a cross-sectioned (a) CreAl alloy-coated and (b) uncoated Zr tube sample after the high- temperature oxidation test.

Fig. 2. (a) and (b) Bright-field TEM images of the interfaces of the coated CreAl alloy layer and Zr alloy after oxidation at 1200 �C. (c) and (d) Dark-field images obtained in the samearea as in (a) and (b).

Fig. 3. (a) HRTEM image of interface and (b) FFT patterns obtained from CreAl alloysides close to the interface.

D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e2305 2301

microstructure of the inter-diffusion layer, SADPs were taken fromthe region marked A in Fig. 4(a), which is shown in Fig. 4(b). The d-

spacings (interplanar distances) of independent diffraction spotsnearest to the (000) transmitted spot were measured as 3.60 and4.16 Å, respectively. The angles between diffraction spots were alsomeasured. These d-spacings and angles are consistent with those ofthe Cr2Zr having a diamond structure [15]. The final indexing of theSADP of Cr2Zr along with a zone axis of [011] is shown in Fig. 4(b).Fig. 4(e) shows EDS profiles for each element recorded along theyellow line in Fig. 4(a), and steep variations in the concentration ofthe Cr and Zr elements were observed at both points of in-tersections of the white dotted line and the yellow line. The weight% values from EDS of Cr and Zr near the interfacial layer closelymatched the stoichiometry of Cr2Zr when converted to atomic %.These results also provide direct evidence supporting the existenceof the inter-diffusion layer. The Al content in the coating layer is lessthan the nominal composition in the CreAl alloy, indicating that Alalloying elements likely diffused from the interface to the surfaceregion during the exposure to high temperature.

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Fig. 4. (a) STEM image of an area close to the CreAl/Zr interface. (b) SADP taken fromthe region marked A in (a). EDS elemental mappings of (c) Cr and (d) Zr in the samearea as in (a). (e) EDS profiles recorded along the yellow line shown in (a). (Forinterpretation of the references to colour in this figure legend, the reader is referred tothe Web version of this article.)

Fig. 5. HRTEM image of inter-diffusion layer between CreAl and Zr matrix and (b) itsFFT patterns.

Fig. 6. (a) STEM image of an area close to the surface of the coated CreAl layer and EDSelemental mappings of (b) O (c) Cr, and (d) Al near the surface region. (e) EDS profilesrecorded along the yellow line shown in Fig. 6(a). (For interpretation of the referencesto colour in this figure legend, the reader is referred to the Web version of this article.)

D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e23052302

Fig. 5 shows the representativeHRTEManalysis obtained from theinter-diffusion layer region.Fig.5(a) shows theatomicarrangementof

the inter-diffusion layerand its corresponding FFTpattern is shown inFig. 5(b). Based ondistances and angles between individual spots, thecrystal structure shown in Fig. 5(a) is identified as the diamondstructure of Cr2Zr along the [011] zoneaxis. The analyzed and indexedFFT pattern shown in Fig. 5(b) is consistentwith the SADP of Fig. 4(b).Asa result,weconcludedthataCr2Zr layerwas formedat the interfacedue to the inter-diffusion of Cr and Zr during the high-temperatureoxidation test. The possibility of a eutectic reaction between Cr andZr is one of the important issues to consider for a Cr or CreAl alloycoated Zr cladding because a eutectic reaction is detrimental to theintegrityof the interfacebetween thecoated layer and thematrix. Themelting point (1673 �C) of the inter-diffusion layer of Cr2Zr is muchhigher than the eutectic temperatures (1332 and 1592 �C) of bothelements [16]. This indicates thatonce thestableCr2Zr layer is formed,it canprevent or delay the onset of the eutectic reaction to a relativelyhigher temperature.

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Fig. 8. Enlarged STEM image of the surface region of the CreAl alloy layer shown in

D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e2305 2303

In contrast to microstructure near the interfacial region, com-plex microstructures were observed near the outer surface region,as shown in Fig. 6(a). Fig. 6(b)e(d) show EDS elemental mappingalong the cross-section near the surface region of the CreAl coatinglayer. Fig. 6(e) shows the EDS profiles from the surface to thecoating layer, which is measured along the yellow line of Fig. 6(a).These results indicate that the coating layer near the outer surfaceconsists of three phases: Cr oxide, Al oxide, and CreAl, as indicatedin Fig. 6(e). The Cr oxide phase was formed on the outer surface ofthe coated layer, and its thickness was about 1 mm. The CreAl alloylayer, including the Al oxide layer, was observed below the Cr oxidelayer. Although the distribution of the Al oxide phase is uneven andsomewhat irregular in some areas, it is generally distributed in theform of a long continuous strip lying perpendicular to the surface ofthe coatings.

For a more detailed study of Cr oxidation states at the outermostsurface, XPS analyses were performed. Fig. 7 shows a Cr 2p3/2spectra core obtained at the surface of the coated CreAl layer afterhigh-temperature oxidation. The overlapped peaks, correspondingto different chemical states in the surface region, were resolved bycurve fitting processes. As a result, the Cr 2p3/2 spectra core can befitted into three peak components at the band edges of about 575.5,576.7, and 578.3 eV, attributable to metallic CrO2, Cr2O3, and CrO3,respectively. These values closely match the values reported inprevious literature [17e19]. From the peak areas and atomicsensitivity factors, the relative concentrations of CrO2, Cr2O3, andCrO3 were determined as 22.19, 57.99, and 19.82%, respectively.Therefore, we concluded that the Cr oxide formed on the outermostsurface of the CreAl alloy after high-temperature oxidation waspredominantly in the form of Cr2O3, together with CrO2, and CrO3.

The absence of peaks for metallic elements of Cr in the Cr 2p3/2spectra core obtained from the oxidized sample implies that the Croxide layer is thicker than the probing depth of the XPS technique(around 8e10 nm) [20e22]. Therefore, the XPS analysis resultsrepresent elemental characteristics of a very thin section of thesurface and cannot be considered to represent the characteristics ofthe overall oxide layer. For microstructural characterization of amore representative oxide layer formed on the CreAl alloy layer,the cross-sectional area near the surface region containing theentire oxide layer was characterized by STEM. Fig. 8(a) shows thebright-field STEM image obtained at the surface region. The darkerarea at the top (indicated by the white arrow) is the Cr oxide layerwith a thickness of about 0.79 mm. The CreAl alloy layer below theoxide layer shows equiaxed and smaller grains when compared to

Fig. 7. Multi-peak fitted Cr 2p3/2 spectra core taken from the surface of the CreAl alloythat was oxidized at 1200 �C for 300 s.

Fig. 6 (a). (b) Experimental HRTEM image obtained at the dotted rectangle area in (a);the green rectangle represents the superposed simulated HRTEM image. (c) FastFourier transform (FFT) pattern obtained from (b). (d) A series of the simulated HRTEMimages of the proposed Cr2O3 viewed along the <4401> as a function of objective lensdefocus, from �50 to 50 Å, and the specimen thickness, from 10 to 20 nm. (d) simu-lated DP with zone axis of <4401>. (For interpretation of the references to colour inthis figure legend, the reader is referred to the Web version of this article.)

the CreAl layer near the interface between the coated layer and Zrmatrix. HRTEM observations were performed to precisely deter-mine the crystal structure of the Cr oxide layer near the surface(shown as the dotted red rectangle area in Fig. 8(a)), and the resultsare shown in Fig. 8(b). An FFT pattern of the region in Fig. 8(b) isshown in Fig. 8(c). Distances and angles between individual spots inthe FFT pattern were quantified, and their indexing is presentedabove each spot. The analyzed structure of the oxide layer is inagreement with the atomic arrangement of hexagonal close-packed (HCP) Cr2O3 along the [4401] zone axis. The NCEMSS soft-ware was used to obtain simulated lattice images and diffractionpatterns of Cr2O3. Fig. 8 (d) shows a series of simulated HRTEM

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D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e23052304

images of the Cr2O3 along the zone axis of [4401] as a function ofobjective lens defocus, from �5 to �15 nm, and specimen thick-ness, from 10 to 30 nm. A simulated HRTEM image assuming anobjective lens defocus of 50 and a specimen thickness of 15 nmwassuperimposed as the green rectangle onto the actual image inFig. 8(b), and the simulation corresponded well with the actualresult. The atomic d-spacing and angles of simulated DPs with azone axis of <4401> (Fig. 8(e)) were also in agreement with that ofexperimental DPs shown in Fig. 8(c).

The Al oxide phase near the surface region was studied usingHRTEM, and the analyzed results are shown in Fig. 9. Like the EDSanalysis in Fig. 6, the brighter area in the bright-field TEM image ofFig. 9(a) is aluminumoxideand the restof the region is theCreAlalloymatrix. Fig. 9(b) shows the HRTEM image obtained from the regionmarked A in Fig. 9(a). The corresponding FFT patterns Fig. 9(b) andtheir indexing are shown in Fig. 9(c). The experimental atomic

Fig. 9. (a) BF-TEM image obtained from the region containing the Al oxide phase layers neaFFT images are shown in (c) and (e), respectively. (f) shows simulated lattice image by the

arrangement and the analyzed crystal structure of region A corre-sponds to HCP Al2O3 along the [0110] zone axis. The microstructuralcharacterization of region B is also determined by experimentalHRTEM and FFT pattern analysis, as shown in Fig. 9(d) and (e),respectively. Formorepreciseobservationof theatomicarrangement,inverse FFT imaging using peaks in Fig. 9(e) are shown in Fig. 9(f).Indexingof FFTpatterns indicates that thecrystal structureof regionBis a BCC structure along the [111] zone axis. Therefore, the darkerregion in Fig. 9(a) represented the CreAl alloy matrix, as determinedby the analysis of the crystal structure and chemical properties(Fig. 6). Most of the options for ATF cladding investigated by variousresearch groups consist ofmaterials that formprotective oxides, suchas chromium, aluminum, and silicon because of their stability insteamandmuch lowerparabolic oxidation rate, roughly twoordersofmagnitude lower than that of zirconium [14,23e26]. The oxidation ofthe CreAl alloy can be explained by the initial formation of a Cr2O3

r the surface. HRTEM images of the regions indicated by (b) A and (d) B in (a) and theirinverse FFT of Fig. (e).

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D.J. Park et al. / Nuclear Engineering and Technology 52 (2020) 2299e2305 2305

oxide layer on the surface. As the exposure time in the high-temperature steam environment increases, a continuous aluminalayer develops near the outer surface of the coated CreAl alloy layer.Eventually, both the Cr2O3 and alumina layers result in increasedoxidation resistanceof theCreAlalloywhencompared to thatof pureCr, which only forms the Cr2O3 layer on its surface. The presence of analumina layer will act as an additional barrier against diffusion ofoxygen into the Zr metal.

4. Conclusions

CreAl alloy-coated Zr nuclear fuel cladding samples wereoxidized in steam at 1200 �C to validate their high- temperatureoxidation resistance and ascertain their potential as a candidate forATF cladding. After high-temperature oxidation testing, the micro-structures near the interface between the coating layer and Zrmatrixand near the outer surface region were characterized using variousanalytical techniques. Based on the results, themain conclusions are:

1. After high-temperature oxidation, a thick ZrO2 layer, as well asan oxygen-stabilized a-Zr(O) layer, was formed on the uncoatedZr tube sample. In contrast, there was a very thin layer ofchromium oxide on the surface of the sample with the CreAlalloy coating and little oxygen-stabilized a-Zr(O) layer in theZr matrix of the coated tube sample. This confirms that theCreAl alloy layer effectively protected the Zr matrix from the1200 �C steam exposure.

2. Although the diamond-structured Cr2Zr inter-diffusion layerwas formed at the interfacial region between the CreAl coatinglayer and the Zr matrix, it was very thin, measuring about1.145 mm, despite the long exposure at high temperature.

3. The CreAl coating layer showed complex microstructures nearthe outer surface region because of oxygen diffusion into theCreAl alloy matrix, while the columnar structure near theinterface was maintained after high-temperature oxidation.

4. Cr oxide phases such as Cr2O3, together with CrO2, and CrO3were present near the outer oxide surface; the predominantphase was Cr2O3. The CreAl alloy layer below the Cr oxideshowed a continuous long strip of an Al2O3 layer perpendicularto the surface. As a result, we concluded that this combination ofCr and Al oxide layers played a crucial role during exposure athigh temperature and resulted in improved oxidation resistancecompared to pure Cr.

Declaration of competing interestCOI

The authors declare that they have no known competingfinancial interests or personal relationship that could haveappeared to influence the work reported in this paper.

Acknowledgements

This work was supported by the National Research Foundationof Korea (NRF) grant funded by the Korea government (MSIP) (No.2017M2A8A5015058).

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