Synchrotron radiation-based materials characterization techniques shed light on molten salt reactor alloys

Synchrotron radiation-based materials characterization techniques shed light on molten salt reactor alloys 1 first-author https://orcid.org/0000-0003-2221-8644 1 2 corresp Corresponding author, wang.dejun@mee.gov.cn Corresponding author, wang.dejun@mee.gov.cn wang.dejun@mee.gov.cn 1 corresp lizhijun@sinap.ac.cn lizhijun@sinap.ac.cn lizhijun@sinap.ac.cn Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China Ministry of Ecology and Environment, Beijing 100135, China Ministry of Ecology and Environment, Beijing 100135, China From a safety point of view, it is important to study the damages and reliability of molten salt reactor structural alloy materials, which are subjected to extreme environments due to neutron irradiation, molten salt corrosion, fission product attacks, thermal stress, and even combinations of these. In the past few years, synchrotron radiation-based materials characterization techniques have proven to be effective in revealing the microstructural evolution and failure mechanisms of the alloys under surrogating operation conditions. Here, we review the recent progress in the investigations of molten salt corrosion, tellurium (Te) corrosion, and alloy design. The valence states and distribution of chromium (Cr) atoms, and the diffusion and local atomic structure of Te atoms near the surface of corroded alloys have been investigated using synchrotron radiation techniques, which considerably deepen the understandings on the molten salt and Te corrosion behaviors. Furthermore, the structure and size distribution of the second phases in the alloys have been obtained, which are helpful for the future development of new alloy materials. Molten salt reactor Alloy materials Synchrotron radiation Shanghai Synchrotron Radiation Facility Molten salt corrosion Tellurium corrosion 1. Introduction 1 A molten salt reactor (MSR), which was first proposed in the 1950s, is a series of nuclear reactors in which fluoride or chloride salts are used as coolants and fuels [ 1 1 ]. The MSR concept was initially implemented in an aircraft reactor experiment (ARE) to offer a pony-size nuclear engine for an aircraft nuclear propulsion (ANP) program, and then in the molten salt reactor experiment (MSRE) by the Oak Ridge National Laboratory (ORNL) as a civilian nuclear power source [ 2 2 ]. MSRs have many apparent advantages and unique applications, such as the utilization of thorium fuel, smal l modular designs, and high-temperature hydrogen production. In the past decade, MSRs have received increased attention owing to their advantages over conventional reactors [ 3 3 ]. In 2011, the Chinese Academy of Sciences (CAS) launched the strategic pioneering science and technology project of thorium molten salt reactor nuclear energy systems (TMSR) [ 4 4 ]. Led by the Shanghai Institute of Applied Physics (SINAP), the TMSR project will result in a 2 MW experimental reactor before 2020 [ 4 4 ]. The reliability and robustness of the structural materials, which will suffer from harsh service environments, including high temperatures, molten salt corrosion, and high irradiation doses, are considered to be the most significant challenges in the development of MSRs. An eligible Ni-Mo-Cr based superalloy (Hastelloy N or INOR-8 alloy) was developed in the ORNL during the 1950s and 1960s and exhibited high-temperature strength and excellent corrosion resistance to molten fluoride salts [ 5 5 ]. A few flaws (helium embrittlement and Te embrittlement) were found after its service in the MSRE from 1965 to 1969, which further motivated the research activities on the Ti-modified and Nb-modified versions in the 1970s [ 6 6 , 7 7 ]. During the development of Hastelloy N and its modified versions, a large amount of research data and many composition-structure-performance relationships were reported by the ORNL. The most important ones were related to molten salt corrosion, Te corrosion, and the roles of key constituents. Unfortunately, the detailed mechanisms of these interesting relationships were not revealed owing to the lack of suitable characterization techniques and theoretical tools at that time. Since the last century, synchrotron radiation theory and the related facilities have developed rapidly. Their apparent advantages over conventional characterization tools include high brilliance, wide energy spectrum, very short pulses, good collimation of emitted radiation, and source cleanliness. Synchrotron radiation techniques have been widely applied in the study of superalloys. Benchmark results include the (1) measurement of the lattice misfit by high energy synchrotron radiation diffraction [ 8 8 ]; (2) determination of local strains and microstructure by synchrotron radiation scanning Laue X-ray microdiffraction [ 9 9 , 10 10 ]; (3) synchrotron tomography of porosity and crack [ 11 11 , 12 12 ]; (4) evaluation of residual stresses [ 13 13 ], and (5) the determination of environment interactions [ 14 14 ]. Synchrotron radiation is expected to solve the remaining problems with alloy materials in MSRs. For example, there were some difficulties in the phase identification of different tellurides on the alloy surface using conventional x-ray diffraction techniques. The interference from other unknown impurity phases and the tiny difference between the different nickel tellurides (NiTe 0.67 , NiTe 0.69 , NiTe 0.70 , NiTe 0.77, and NiTe 2 ) made the precise phase identification impossible. This could be solved by synchrotron radiation X-ray diffraction owing to its higher brilliance. Synchrotron radiation-based material characterization techniques can also be expected to deepen the understanding of the related mechanisms in the MSR alloys, which is required for the further optimization of this alloy or the design of new ones ( Table 1 Table 1 ). 1 1 1 1 N INOR-8 1 1 Ti-modified N 1 1 Nb-modified N 1 1 HN80МTY 1 1 MONICR 1 1 GH3535 1 1 EM-721 1 1 Ni 1 1 Bal. 1 1 Bal. 1 1 Bal. 1 1 Bal. 1 1 Bal. 1 1 Bal. 1 1 Bal. 1 1 Mo 1 1 16 1 1 12.97 1 1 11.71 1 1 13.2 1 1 15.8 1 1 16 1 1 0.07 1 1 Cr 1 1 7 1 1 6.97 1 1 6.78 1 1 6.81 1 1 6.85 1 1 7 1 1 5.7 1 1 Fe 1 1 5 1 1 0.08 1 1   1 1 0.15 1 1 2.27 1 1 4 1 1 0.05 1 1 Mn 1 1 0.8 1 1 0.02 1 1 0.1 1 1 0.013 1 1 0.037 1 1 0.5 1 1 0.086 1 1 Si 1 1 1 1 1 0.03 1 1   1 1 0.04 1 1 0.13 1 1 0.3 1 1 0.065 1 1 Ti 1 1   1 1 1.8 1 1   1 1 0.93 1 1 0.026 1 1   1 1 0.13 1 1 Nb 1 1   1 1   1 1 1.15 1 1 0.01 1 1   1 1   1 1   1 1 Al 1 1   1 1 0.1 1 1   1 1 1.12 1 1 0.02 1 1   1 1 0.08 1 1 W 1 1 0.5 1 1 0.01 1 1   1 1 0.072 1 1 0.16 1 1   1 1 25.2 1 1 C 1 1 0.08 1 1 0.06 1 1 0.043 1 1 0.025 1 1 0.014 1 1 0.05 1 1   In 2004, the SINAP started building the Shanghai Synchrotron Radiation Facility (SSRF), which was fully opened to users in 2009 [ 15 15 ]. When the TMSR team was organized in 2011, many scientists from the SSRF came in and dealt with the problems mentioned above using synchrotron radiation technology. In this article, we will review the related works to demonstrate the new understanding of the microstructural evolutions and failure behaviors of alloy materials for MSRs and clarify the availability of synchrotron radiation applications in this field. The new progress is introduced in three sections: (1) molten salt corrosion, (2) Te corrosion, and (3) alloy design. Today, most of the related studies are carried out in the SSRF. Thus, we give a brief introduction of the beamlines in the SSRF used in these studies. In addition, the more promising applications of synchrotron radiation in this field are discussed. 2. Materials and Methods 1 2.1. Development of Alloy Materials for MSRs 2 During the ANP period, the ORNL was responsible for both the design and building of the ARE, which involved the synchronous screening of fuel, coolant, and alloy materials. In 1950, the fluoride 75% NaF-25% UF4 was firstly proposed as the fuel candidate [ 16 16 ]. Then, the important criterion for the screening of structural materials was the chemical compatibility with molten fluoride salts. In the dynamic corrosive conditions of thermal convection loops, the Inconel 600 alloy operated well [ 17 17 ]. In 1954, the ARE produced 100 MWh over nine days at a peak temperature of 860 °C with the Inconel 600 alloy as the structural material. However, the Inconel 600 alloy can hardly meet the high-temperature strength and corrosion resistance requirements of the MSRE. The ORNL started developing a new alloy based on the Ni-Mo binary system. It was found that the addition of Mo of less than 15 wt. % produces an insufficient high-temperature strength. However, the Mo content was preliminarily limited to 20 wt. % in consideration of the pipe extrusion processability and thermal stability. In the range of 15–20 wt. % Mo, further addition of Mo can lead to better creep properties in the Ni-Mo-Cr-Fe alloys. In view of the unavoidable exposure to hot air, the addition of Cr is necessary for the oxidation resistance of alloys. However, it has been revealed that Cr would be removed from the hotter parts of the loop and deposited in the cooler parts when reacting with UF 4 (more details in section 3). Thus, the Cr content should be as low as possible to obtain the lowest corrosion rate in fluoride salts. Cr contents of 6–8 wt. %, can prevent the oxidation from air at 700 °C but are not enough to induce high molten salt corrosion rates. At the time of the ARE, Cr was always added in the form of cheap Fe-Cr alloys rather than in the expensive elemental state. The presence of minor amounts of Fe ( < 6 wt. %) does not drastically affect the properties of alloys. Based on the above results, several promising nickel-based alloys, codenamed INOR-1 to INOR-9, were melted and evaluated, and INOR-8 ( Table 1 Table 1 ) was found to meet all requirements [ 18 18 ]. The ANP program was discontinued in 1960, and the mission of the program was shifted to the MSRE program. In this period, long-term corrosion experiments and the evaluation of the mechanical properties were carried out on several heats purchased from different manufacturers to ensure that the properties were equivalent to those measured from the laboratory-level INOR-8. An alloy with a composition very close to that of INOR-8 was then commercialized by Haynes as Hastelloy N and played a crucial role in the success of the MSRE. However, examinations of the alloy materials after the shutdown of the MSRE revealed two serious deficiencies. First, the alloy was embrittled by helium due to the transmutation of tramp 10 B [ 19 19 ]. Second, the Te fission products in all alloy materials in contact with the fuel salts resulted in surface intergranular cracking [ 20 20 ]. The critical helium concentration required to embrittle the alloy is so low that reducing the boron concentration is not effective [ 21 21 ]. An effective solution for the helium embrittlement problem is to add IVB and VB group elements (typically Ti) into Hastelloy N; these preferentially form fine MC carbides to trap the helium atoms at their interface with the matrix and prevent the growth of helium bubbles at grain boundaries [ 22 22 ]. The ORNL researchers proceeded with the development of Ti-modified Hastelloy N. At a later time, they observed that the addition of 1 to 2 wt. % of Nb to Hastelloy N could effectively prevent helium and Te embrittlement synchronously. In the new century, the MSR concept has attracted more attention owing to the advantages mentioned above. Thus, the development of structural materials for MSRs has again become an important topic. Based on Hastelloy N, improved versions have been proposed, including the Fe-reduced MONICR alloy [ 23 23 ] and Al-modified HM80M series [ 24 24 ], which exhibit better creep properties and Te corrosion resistance, respectively. In France, a new Ni-W-Cr based superalloy (EM-721) was developed, which can endure potentially higher in-service temperatures [ 25 25 ]. The ORNL is developing some new nickel-based alloys with high-temperature strength higher than that of Hastelloy N for use in fluoride salt-cooled high-temperature reactors (FHRs) [ 26 26 ]. Based on Hastelloy N, the GH3535 alloy has been developed for TMSRs [ 7 7 ], and its composition optimization (Si and C), extensive characterization, and the process development of large-scale components are being carried out. The related synchrotron radiation technique-assisted studies are reviewed in this paper. 2.2. Shanghai Synchrotron Radiation Facility (SSRF) 2 For the SSRF Phase-I program, seven beamlines have been built, namely the macromolecular crystallography (BL17U1) [ 27 27 , 28 28 ], X-ray absorption fine structure (XAFS, BL14W1) [ 29 29 ], diffraction (BL14B1) [ 30 30 ], hard X-ray micro-focusing (BL15U1) [ 31 31 ], X-ray imaging (BL13W1) [ 32 32 ], soft X-ray spectromicroscopy (BL08U1A) [ 33 33 , 34 34 ] and small-angle X-ray scattering (SAXS, BL16B1) beamlines [ 35 35 ]. In this article, we review the studies related to BL14W1, BL15U1, BL08U1A, and BL16B1. The XAFS beamline (BL14W1) at the SSRF is a powerful platform to explore the local structure of materials [ 29 29 ]. At present, standard XAFS data can be collected in transmission and fluorescence yield modes. In addition, the quick-scanning XAFS (QXFAS), X-ray emission spectroscopy (XES), grazing incidence XAFS (GIXAFS), high-pressure XAFS, and time-resolved X-ray excited optical luminescence methods will gradually become available to users in the future. The hard X-ray micro-focusing beamline (BL15U1) of the SSRF is mainly aimed at hard X-ray micro/nano spectrochemical analyses, including micro-beam X-ray fluorescence (μ-XRF), X-ray absorption spectroscopy (XAS), and synchrotron radiation X-ray diffraction (SR-XRD) [ 31 31 ]. The BL15U1 beamline provides high-brightness X-rays with energy ranging from 4.9 to 20.5 keV. It is also capable of micro-focusing as low as ~ 2 μm. The beamline and the experimental end-station were upgraded several times to facilitate the users’ experimental needs and make it more convenient to operate. In the BL15U1 beamline, a motorized x − y − z stage with a high step precision of 100 nm allows hyperfine scanning in the beam for XRF, XRD, and XAS ( Fig. 1 Fig. 1 ). With this stage, the phase distribution, composition distribution, and valence state information of an element can be obtained simultaneously by XRF mode scanning and XRD mode scanning of the same region. The BL08U1A beamline is a soft X-ray beamline with a photon beam energy range of 250 to 2000 eV and is aimed at nano-scale elemental imaging at high spatial and energy resolutions [ 33 33 , 34 34 ]. 2D and 3D imaging of metallic materials can be performed in the scanning transmission X-ray microscopy (STXM) end station. The STXM combines high spatial and energy resolutions of the chemical states of near-edge absorption fine structure spectroscopy (XANES). The scanning precision of piezo stages is approximately 5 nm, and the scanning range can be selected from several microns to several hundred microns. Coherent diffraction imaging (CDI) can offer higher spatial resolution than STXM, which is also installed at the STXM chamber ( Fig. 2 Fig. 2 ). The highest resolution of CDI is approximately 10 nm, derived from a power spectral density analysis of the reconstructed image using scanning CDI reconstruction software. The SAXS beamline (BL16B1) at the SSRF provides a powerful support for studying the microstructure of polymers, fibers, and nanostructure/mesoporous materials [ 35 35 ]. The techniques available in the beamline include SAXS, wide-angle X-ray scattering (WAXS), anomalous small-angle X-ray scattering (ASAXS), grazing incident SAXS (GISAXS), and time-resolved simultaneous SAXS/WAXS on structural transitions in the sub-second time region and partly ordered systems with a scaling of 1 to 240 nm in real-space. More techniques will be implemented at the BL16B1, including the USAXS technique based on the Bonse–Hart camera system and micro-focus SAXS. Additional common in-situ devices to facilitate the use of this beamline will be developed. A complete SAXS data analysis platform will be established for data pretreatment, SAXS and WAXS data analyses, etc. 3. Molten Salt Corrosion 1 In most high-temperature environments, the desired corrosion resistance of materials is achieved by the formation of a compact and protective oxide film on the alloy surface. For high-temperature applications in oxygen-containing environments, alloy elements, such as Cr and Al, are commonly used to facilitate the formation of protective oxide films to retard further oxidation. However, in fluoride salt systems, any such protective oxide scales are not stable and can be easily dissolved by the fluxing action of molten fluoride salts and, thus, cannot be relied upon for corrosion protection. The corrosion of alloys in molten salts has been extensively studied [ 14 14 , 37 37 - 43 43 37-43 ] and reviewed [ 44 44 - 48 48 44-48 ], since the foundational work for the use of molten salts in nuclear energy applications was performed at the ORNL from the 1940s to the 1970s. Briefly, the molten salt corrosion of alloys is driven by a variety of factors, including the thermodynamics of corrosion reactions [ 42 42 , 43 43 ], impurity effects [ 14 14 , 40 40 , 41 41 ], thermal gradients [ 49 49 , 50 50 ], and galvanic corrosion induced by the difference of electromotive potential in materials [ 51 51 , 52 52 ]. During the corrosion process of alloys in molten salt, the elements that form fluorides with more negative free Gibbs energies would preferentially react with molten salt and transfer from the alloy into the molten salt. The list of fluoride-forming elements used in Ni-based and Fe-based alloys is, from the least to the most thermodynamically favorable, as follows: Al, Cr, Fe, Ni, Mo, and W. In view of the greater stability of molten fluoride salts (LiF, BeF 2 , NaF, KF, etc.) over that of potential corrosion products, the corrosion of these elements should, in theory, not occur. However, the unavoidable impurities in the molten salts, including H 2 O, HF, and metallic ions (Ni 2+ , Fe 2+ ), would react with the alloys by redox reactions and cause considerable corrosion, as reported in [ 41 41 ]. Techniques based on synchrotron radiation, such as XRF, XANES, and STXM, are powerful for measuring the elemental concentration and chemical state of reaction products at the micro and nanoscales, which can reveal the type of chemical reaction and the corrosion mechanism. However, to date, few studies on these methods have been reported in the literature. Liu et al. [ 53 53 ] were the first to apply μ-XRF and SR-XRD techniques at the SSRF to evaluate the corrosion behavior of different Ni-based alloys. The μ-XRF mapping from the cross-section shows the poor corrosion resistance of all the alloys to molten salts, and that the alloys are significantly depleted in Cr. Interestingly, Mo 2 C was detected by SR-XRD, a result of the galvanic reaction between the alloys and the graphite crucibles. This phenomenon can also occur in real molten salts reactors because they use graphite as a neutron moderator. In addition, small amounts of Cr 2 O 3 , which should not be stable in molten salts, were also found to form in the corroded Inconel 600 and Hastelloy C-276 alloys, indicating the high content of oxygen impurities in the FLiNaK salts. It should be noted that such a small amount of Mo 2 C or Cr 2 O 3 is difficult to detect in lab XRD. Another study on the corrosion behavior of nickel alloys based on synchrotron radiation techniques was reported by Ye et al. [ 14 14 ]. As mentioned above, the presence of oxidizing impurities greatly facilitates the corrosion of alloys in the molten salts. Among the impurities, the role of H 2 O in the corrosion process has been determined. HF can form during the reaction between H 2 O and the fluoride ions and would attack most metal elements in the alloys to form the corresponding fluorides. So far, the concentration of H 2 O in the fluoride salts can be controlled to a level of less than 10 ppm by several methods [ 43 43 , 54 54 , 55 55 ]. In contrast, studies on the role of other metallic ion impurities (e.g., Fe +2 , Fe +3 , Cr +2 , Cr +3 , and Ni +2 ) in the corrosion process are still limited. In other words, besides the redox reaction, it is not clear whether some other types of reaction, as well as composition changes in the precipitates, may occur in the alloys. Ye et al. applied STXM and XANES with the assistance of the stage with high positional accuracy ( Fig. 1 Fig. 1 ) to characterize the corroded and control Hastelloy N alloys at the BL15U1 beamline. The XANES results showed that no oxidized compound of Fe formed in the corroded specimen, indicating that only a redox reaction, e.g., Cr + Fe 2+ =Cr 2+ + Fe, occurs in the alloys surface, causing depletion of Cr in the alloys. This result suggests that only the redox reaction can occur during the molten salt corrosion ( Fig. 3e Fig. 3e ). In addition, a different Cr concentration in the M 12 C carbides and matrix after corrosion was detected by STXM, indicating that Cr diffused from M 12 C carbides to the matrix, which could not be measured clearly by TEM/EDS. As shown in Fig. 3d and e Fig. 3d and e , the depletion and enrichment of Cr can be observed before and after the corrosion process, respectively. The steep concentration gradient of Cr in the matrix, which results from the redox reaction, would further drive the diffusion of Cr atoms from the carbide into the matrix. This may be the first work based on SR-STXM method to investigate the properties of Ni-based alloys. The results obtained in the nanoscale by STXM and XANES are useful for our understanding of the effect of metallic impurities (e.g., Fe +2 , Fe +3 , Cr +2 , Cr +3 , and Ni +2 ) on the corrosion of alloys in FLiNaK salts. 4. Te Corrosion 1 4.1. Te Distribution by SR-XRF 2 As mentioned above, Te atoms diffuse along the surface grain boundaries and then cause the intergranular cracking of alloys. In general, the diffusion mode (grain boundary or lattice) of impurities in metals transforms in the moderate temperature range. Thus, it is necessary to investigate the diffusion of Te atoms in pure nickel and the reaction between them in the moderate temperature range (500–1000 °C) to understand the Te embrittlement in the GH3535 alloy. In such an investigation, the characterization method used to determine the Te distribution is the most important aspect. XRF spectroscopy is a powerful non-destructive method for the analysis of trace elements in material science research, and BL15U1 enables XRF multi-element mapping and quantitative analysis with a sub-ppm level detection limit and a micro- or sub-micro level beam size [ 31 31 ]. Thus, the cross-sectional micro-XRF maps of Te in the samples, which are exposed to Te vapor at 500–1000 °C, were examined with a monochromatic 5 keV X-ray beam in BL15U1 [ 56 56 ]. For comparison, electron probe microanalysis (EPMA) examinations were also carried out. The typical results for the samples exposed at 1000 °C are shown in Fig. 4 Fig. 4 . SR-XRF revealed a higher Te diffusion depth than EPMA, which indicates the higher sensitivity to Te atoms in the SR-XRF detection. The critical value of the Te concentration for intergranular cracking can be very low, but the precise measurement of the Te distribution is necessary. It has been reported [ 57 57 ] that the diffusion depth of Te was significantly underestimated by the EPMA measurements and was smaller than that of intergranular fractures observed from the tensile specimens. This indicated that the critical damage level of Te for GH3535 alloy is lower than the EMPA detection lim it. From Fig. 4 Fig. 4 , it can be seen that the diffusion depth measured by SR-XRF can reflect the damage behaviors by Te corrosion more accurately than EPMA. Unfortunately, the low lateral resolution of SR-XRF detection in this study cannot reveal the enrichment of Te at grain boundaries effectively. A nano-focusing (100 nm) fluorescence system has been built on BL15U1, and improvements to the flux and efficiency of detection are underway [ 31 31 ]. 4.2. Local Structure of Te atoms in alloys 2 Despite the predominant role of Te corrosion at the grain boundaries, its diffusion and enrichment in the lattice can also influence the microstructures and mechanical properties of GH3535 alloy. The occupied sites of Te atoms in the FCC matrix and their effects on the lattice are still unclear. Limited experiment results have indicated that the lattice of the matrix expands after Te corrosion. Thus, the local structure of Te atoms in the corrosion products or the matrix lattice was investigated by extended XAFS (EXAFS) and first-principles calculations [ 58 58 ]. As shown in Fig. 5 Fig. 5 , the radial distribution functions (RDFs) of the corroded and control specimens of pure Ni and Te were extracted from their k 2 -weighted EXAFS. The absence of a prominent peak at 2.6 Å for Te in the RDF indicates that Te clusters did not exist in the Te-exposed sample, and the similarity of the local structure around Te atoms between corroded and Ni samples proves that Te atoms randomly solubilize in FCC Ni to form the substitutional solid solution. Provided Te atoms are surrounded by Ni atoms in the FCC Ni, the fitting curve of the EXAFS signal in R-space with the contribution from each of the three nearest neighbor shells agrees well with the experimental curve. Moreover, the bond length for the nearest three shells is larger than that predicted with theoretical data of pure Ni. EXAFS proved that the lattice expansion of the corroded Ni results from the substitution of Te. This conclusion can also be verified by DFT calculations. In the case of the nearest neighbor Te–Te pair, the negative energy value indicates that such a configuration is energetically unfavorable in the Ni substrate. To overcome the Te corrosion problems, researchers are trying to optimize the chemical composition and microstructure of alloys. It is worth noting that high-chromium alloys always exhibit higher Te corrosion resistance. Using XANES, one Ni-18Cr alloy was corroded by Te vapor at different temperatures (600–1000 °C), and the local structure of Te atoms in the corroded samples was determined [ 59 59 ]. Fig. 6 Fig. 6 displays the XANES results of the Te K-edge. From the peak positions in the Fourier transform (FT) curves of these samples, the Cr-Te scattering contribution can be observed, which indicates the existence of chromium telluride as a corrosion product. In the case of the specimens corroded at 900 °C, a much lower R position indicates the dominance of the Ni-Te contributions, which correspond to the formation of partial Ni 3 Te 2 . Using wavelet transform (WT) analysis, the corrosion product was determined to be a substitutional Ni-Cr-Te solid solution in the specimens corroded at 1000 °C. The XANES has proved to be a powerful tool for exploring the structure and composition of corrosion products, which can deepen our understanding of the protection mechanism of certain tellurides. 5. Alloy Design 1 5.1. Lattice parameter measurement of minor M 6 C carbides by HESXRD 2 Si is always used in small amounts as a deoxidizer during the melting of nickel-based superalloys. With a few exceptions, as noted below, its presence in Hastelloy N has significant effects on the microstructures and properties of this alloy [ 60 60 ], which indicates a large potential for the optimization of Si concentration. To systematically determine the role of Si, the morphology, microstructure, composition, and phase transformation of the carbides in the GH3535 alloys were investigated, with different Si concentrations, in the cast state, solid-solution state, and thermal exposure state, respectively. It was found that Si addition stabilizes M 6 C carbides at high temperatures in GH3535 alloys [ 61 61 ]. M 6 C carbides, which belong to the space group Fd3m and have three forms (A 3 B 3 C, A 4 B 2 C, and A 2 B 4 C), are characterized by chemical and structural flexibility [ 62 62 ]. No general agreement, about the atomic occupancy of Si (A, B, or C) in M 6 C carbides in other alloys, has been reached by conventional characterization techniques [ 63 63 - 65 65 63-65 ]. The interaction of Si atoms with the neighboring atoms in M 6 C carbides was also not clear until the combined utilization of the synchrotron radiation techniques and first-principles calculations [ 61 61 ]. Assuming one Si atom occupies the four different sites (16d, 32e, 48f, and 16c) in the Ni 3 Mo 3 C system, the equilibrium lattice parameters and site occupancy energies were calculated and compared with those of the initial Ni 3 Mo 3 C without Si doping. The equilibrium lattice was found to shrink when the 16d, 32e, and 48f sites were occupied, but it was found to expand when Si atoms replaced C atoms at the 16c site. The actual lattice parameters should be examined to validate these results. In other studies, carbides for XRD were always anodically extracted with a cathode in a mixed solution, typically 25% HCl-75% methanol. However, this technique is not suitable for our small sample (10 × 10 × 1 mm 3 ). In the sample with 0.05 wt. % Si, the M 6 C carbides extracted for XRD were largely insufficient. However, the alloying effects of a small number of Si additions in M 6 C carbides could be out of the detection limit of laboratory XRD. Thus, high-energy synchrotron X-ray diffraction (HESXRD) was applied to examine the lattice parameters of the M 6 C carbides in the matrix without extraction. In the HESXRD experiment, the high brilliance and good collimation can ensure a relative error as low as ∼2 × 10 −4 for the lattice spacing. From Fig. 7 Fig. 7 , it can be seen that the lattice parameters of M 6 C carbides decrease with increasing Si concentrations, and the decrease rate becomes smaller with increasing Si concentrations, which is slightly different from the linear decrease trends observed in other alloys by laboratory XRD equipment [ 66 66 ]. In M 6 C carbides, Si is just a doped element rather than a required component. It seems reasonable that there exists a saturated content for the doped Si atoms, and then a saturated effect of lattice shrinking, as shown in Fig. 7c Fig. 7c . Such a saturation effect can also be observed in the formation energy vs Si content curve for the Si-doped Ni 3 Mo 3 C system obtained by first-principle calculations. In that study, HESXRD could reveal the tiny but interesting details about the alloying effects of Si, which had not been reported previously. By combining the calculation results and HESXRD data, it can be deduced that the 16d site, rather than other sites, is preferentially occupied by Si atoms in the Ni 3 Mo 3 C carbides. 5.2. Optimization of W content in Ni-xW-6Cr alloy by μ-XRF, μ-XRD, and μ-XANES 2 The Ni-W-Cr-based superalloy has been considered a potential candidate structural material for molten salt reactors operating above 800 °C, which is designed to use W as a solid-solution strengthening element, replacing the counterpart Mo in Hastelloy N [ 25 25 ]. Preliminary studies indicate that the strength increases significantly with increasing W concentration in the Ni-xW-6Cr alloys [ 67 67 ]. In addition, the Ni-26W-6Cr alloy exhibits a corrosion resistance comparable to that of GH3535 alloy [ 68 68 - 69 69 68-69 ]. Because the alloy materials in MSRs are exposed to air and molten salts simultaneously, the oxidation behavior of the alloys should be considered. Unfortunately, the role of W in the oxidation process of superalloys is still unclear [ 70 70 - 73 73 70-73 ]. In Hastelloy N, 6–8 wt. % Cr additions are just enough to achieve an oxidation resistance of up to 750 °C. Thus, the oxidation resistance of the Ni-xW-6Cr alloys is questionable. In a recent work [ 36 36 ], the oxidation resistance of the Ni-xW-6Cr (X=5–30) alloys at high temperature was investigated. The resistance was found to increase with the W concentration, although not steadily, and the Ni-25W-6Cr alloy exhibited the best resistance. The phase constituent and chemical state of oxide scales were characterized by μ-XRF, micro XRD (μ-XRD), and micro XANES (μ-XANES) at BL15U1. The distribution of oxides and related oxidation reactions in the Ni-xW-6Cr alloys are illustrated in Fig. 8 Fig. 8 and were identified by μ-XRF and μ-XRD at 20 keV. As a secondary acceptor of the inward diffused oxygen, the presence of W facilitates the formation of Cr 2 O 3 and NiCr 2 O 4 in the regions with lower concentrations of Cr ( Fig. 9 Fig. 9 ). In sequence, the increase in the W concentration in the Ni-xW-6Cr alloy improves its oxidation resistance below 25 wt. %. When the concentration of W exceeds 25 wt. %, the excessive W concentration consumes Cr 2 O 3 to form CrWO 4 (which is also found in the oxidized Ni-25W-6Cr alloy, as shown in Fig. 9 (h) Fig. 9 (h) ). Therefore, restraining the formation of protective NiCr 2 O 4 . The existence of CrWO 4 destroys the compactness of NiCr 2 O 4 and provides the breakaway throughout the scales as the diffusion paths for oxygen and metallic ions. It is clear that, without the high spatial resolution of synchrotron radiation technologies, it is hard to determine the existence of CrWO 4 in the scales. Moreover, it was found that the valence state of W in the corrosion products ( Fig. 10 Fig. 10 ) is between 4+ and 6+ rather than the strict 6+. This indicates that the tungsten oxides in the Ni-25W-6Cr alloy are not strict stoichiometric WO 3 . In fact, it has been reported that the chemical composition of tungsten oxides ranges from WO 2.72 to WO 2.9 [ 74 74 ]. Such deviation from the strict valent state of the oxides may also play an important role in the diffusion process of W ions. The author suggested that the optimum W content is 25–30 wt. % from the aspect of oxidation resistance. 5.3. Size Distribution Study of SiC Nanoparticles in Ni-SiC by USAXS 2 As mentioned above, the helium embrittlement problem can be effectively reduced by the addition of Ti, Nb, Zr, and Hf, which form fine MC carbides to trap the helium atoms at their interface with the matrix and prevent the growth of helium bubbles at grain boundaries [ 22 22 ]. From another perspective, the direct addition of molten salt corrosion-resistant nanoparticles into the matrix could be a promising solution. Therefore, bulk Ni–SiC NP composite materials have been developed for their potential application in MSRs [ 75 75 ]. This material exhibits stronger helium absorbing capability than pure nickel and hence mitigates helium embrittlement. The density and size distribution of the particles directly determine the capacity for helium trapping, which should be measured accurately. Xie and her co-workers carried out such measurements in a Ni–SiC NP composite by USAXS [ 75 75 ]. They found that SiC nanoparticles are almost evenly distributed in the pure Ni matrix. By modeling the USAXS data, the size distribution, number density, and interparticle distances of the SiC nanoparticles were obtained, which agree with those obtained from TEM ( Fig. 11 Fig. 11 ). The appropriate usage of USAXS in the simplified model materials reveals its potential for characterizing nanosized MC carbides in modified Hastelloy N. It has been found that the addition of different MC carbide-forming elements leads to different helium trapping capacities. USAXS could provide an interpretation for such capacities from the point of microstructures, namely the presence of MC carbides in the modified Hastelloy N alloys. 6. Summary and Perspective 1 Synchrotron radiation techniques have already proved to be powerful for the study of alloy materials for MSRs. The related studies have advanced the understanding of molten salt and Te corrosion from a microscopic point of view. Moreover, the applications of synchrotron radiation techniques have promoted the optimization of the GH3535 alloy with more appropriate Si content, and the design of new alloys, such as a strengthened dispersion alloy. So far, most studies based on synchrotron radiation techniques were aimed at the Hastelloy N or its improved versions, such as GH3535. New alloy materials for MSRs would receive more and more attention and would expand the application of synchrotron radiation techniques. The mechanical properties, atomic configuration, and precipitates (MC carbides or γ’ phases), to name a few, could be investigated. The atomic configuration of these new additional elements, such as Nb, Ti, Al, and W, in the different alloys ( Table 1 Table 1 ), should be explored by XAFS to determine their strengthening mechanism. Preliminary experiments for the W atoms in a Ni-W-Cr alloy are underway. USAXS and HERXRD can help us to design the appropriate distribution and interfacial mismatch of nano-sized MC carbides in the Ti-modified and Nb-modified alloys, which are related to their strengthening and helium trapping effects. The mechanism of Te corrosion resistance from Nb and Al additions is still unclear. The formation of protective layers containing Nb and Al on the surface of alloys is a possible scenario, which can be examined by STXM and XAS. Overall, synchrotron-based material characterization techniques can shed light on alloy materials for MSRs, and more investigations should be performed. Furthermore, the experimental capability of SSRF can be enhanced by the update of Phase-I beamlines [ 76 76 - 81 81 76-81 ], and the Phase-II beamline project (including sixteen new beamlines), which was officially started on 20 November, 2016, with a construction period of 6 years. It is expected that the new beamlines will create opportunities for the study of MSR alloy materials. 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(Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, ChineseNuclear Society and Springer Nature Singapore Pte Ltd. 2020 This is a post-peer-review, pre-copyedit version of an article published in Nuclear Science and Techniques. The final authenticated version is available online at: http://dx.doi.org/10.1007/s41365-019-0719-7 http://dx.doi.org/10.1007/s41365-019-0719-7 . 2020 Nuclear Science and Techniques 1 31