1. Introduction
Molten salts exhibit a broad spectrum of properties, rendering them highly suitable for application in advanced energy generation and storage systems. The benefits of molten salt–based systems, particularly for nuclear industry applications, arise from their physical and chemical properties: high boiling point and, as a consequence, low vapor pressure; good heat transfer capacity; wide electrochemical stability window; resistance to ionizing radiation; absence of neutron moderators; and good solubility of actinide compounds [
1,
2,
3,
4].
Currently, two primary technological frontiers are advancing towards the application of molten salts in power engineering on a semi-industrial scale: in concentrated solar power (CSP) systems and in the nuclear industry as primary or secondary coolants in both fission and fusion systems, as well as the media for spent nuclear fuel reprocessing [
5,
6,
7,
8,
9,
10,
11,
12,
13,
14]. Molten salt reactor (MSR) technology was initially demonstrated in the 1950s to 1960s at ORNL [
15]; significant renewed interest and research efforts were notably intensified from the 2010s [
16]. The gap between the initial historical demonstration of the technology and the current renaissance is attributed to a number of factors, including unresolved issues with insufficient corrosion resistance of the construction materials, the complexity of operating molten salt reactors, and the substantial level of funding required for implementing such nuclear power installations. The comprehensive spectrum of challenges associated with the deployment of MSRs is described in the IAEA Technical Report 489 [
17]. One of the critical issues is the lack of suitable structural materials capable of withstanding prolonged operation under the severe conditions inherent to MSR systems. Two types of molten salt systems are considered for use in MSRs, i.e., based on fluorides, which were tested in the past, and chlorides, which are considered as prospective working media. Among fluorides, there are two principal compositions of the solvent melt—a mixture of lithium and beryllium fluorides (FLiBe) and the ternary eutectic mixture of lithium, sodium, and potassium fluorides (FLiNaK) [
18]. The latter salt is more promising because it is characterized by higher solubility of actinide fluorides [
19,
20,
21]. The current research focused on studying structural material compatibility with FLiNaK-based molten fluoride salts.
Possible causes of corrosion in molten halide media have been extensively investigated worldwide [
22,
23,
24,
25,
26,
27,
28,
29,
30,
31,
32,
33,
34,
35,
36,
37,
38,
39]. The primary factors influencing corrosion are generally considered to be the exposure temperature, the nature of the fused electrolytes, the type and content of impurities in the salt, the purity of the surrounding atmosphere (presence of moisture and oxidants), and the composition of the structural material itself. Despite numerous studies, insufficient attention has been devoted so far to the effect of the microstructure of the materials on their corrosion resistance. Existing data concerning corrosion phenomena in molten halides and material structure are somewhat controversial and do not allow a sensible connection between an alloy’s internal structure changes and its corrosion performance in a molten salt environment to be established. For example, aging the Ni-based alloy VDM
® Alloy C-4 at 550 °C for 2500 h resulted in the formation of a Ni
2(Cr,Mo) phase, which showed some positive effect on the alloy’s corrosion resistance in an acidic KCl–AlCl
3 melt [
39]. Improvement in the corrosion resistance of a C-4 type alloy in the same melt aligned well with the results of Tawancy and Alhems [
40] for aqueous systems. They also observed that the rate of corrosion of a C-4 type alloy with a long-range ordered (LRO) structure was lower compared to its initial annealed state. Formation of dispersion hardening particles of the Ni
2(Cr,Mo) ordered phase led to a reduction in the alloy’s corrosion equilibrium potential, primarily due to enhanced interatomic interactions [
39].
However, in a study of a model Ni–33 at. % Cr alloy corrosion, Fei Teng et al. [
41] observed degradation of a Ni
2Cr (MoPt
2-type) long-range ordered phase within the Ni–Cr binary system. They reported that the formation of the Ni
2Cr phase accelerated the corrosion process in molten chlorides. This acceleration was attributed to two primary factors: the anisotropic corrosion behavior of the LRO phase and the internal lattice strain induced by the LRO structure. In another study [
42], the same authors declared that the cold-rolling process increased the susceptibility of 316 L steel to corrosion in molten FLiNaK salt.
Muransky et al. [
43] investigated the impact of microstructural changes under plasticity-imparting conditions on alloy corrosion performance in molten salts. They showed that the stored dislocations and dislocation substructures formed during high-temperature creep (HTC) facilitated mass transfer towards the corrosion-affected layer through intragranular diffusion of the alloying elements. Subsequently, the recrystallized fine-grained microstructure of the corrosion-affected layer enhanced transfer to the salt-exposed surface via intergranular diffusion. This enhanced mass diffusion accelerated molten salt corrosion of the alloy, significantly shortening its lifespan under operational conditions.
However, it appears that one of the most significant microstructural changes that affects intergranular corrosion (IGC) is the formation of carbide or topologically close-packed (TCP) phases. Metallographic analysis of samples of AISI 316 steel after corrosion tests in a LiF–BeF
2 melt at 700 °C revealed the presence of grain boundary precipitation of the Cr
7C
3 phase, thus confirming carbon and chromium diffusion towards the grain boundaries, causing subsequent initiation of IGC processes [
33]. Similarly, IGC was detected in AISI 316L, 316Ti, and 321 austenitic stainless steels after their exposure in melts based on a NaCl–KCl equimolar mixture at 750 °C [
44]. The authors proposed a mechanism of corrosion of stainless steels in molten chlorides that includes the following stages: deposition of chromium-containing carbides along the grain boundaries and formation of galvanic pairs between the chromium-depleted parts of the grains of austenitic alloys and the carbide phases. Later, the same authors indicated that intermetallic topologically close-packed χ phases containing chromium and molybdenum were formed in low-carbon steels as a result of heating to 750 °C, also inducing IGC processes [
45].
The corrosion behavior of the corrosion-resistant alloy Hastelloy
® G-35
®, the corrosion and heat-resistant alloy VDM
® Alloy 600 or Nicrofer
® 7216, and the corrosion-resistant alloys VDM
® Alloy C-4 or Nicrofer
® 6616 and VDM
® Alloy 625 or Nicrofer
® 6020 was also investigated in fused KCl–AlCl
3 at 450–650 °C with exposure times of up to 1000 h [
46]. Increasing temperature noticeably increased the corrosion rates and changed the corrosion process nature. Transmission electron microscopy revealed that Me
23-nCr
nC
6 type carbides (for VDM
® Alloy 600) and intermetallic TCP phases (such as sigma-phase in case of Hastelloy
® G-35
®, VDM
® Alloy C-4, and VDM
® Alloy 625) were formed during prolonged high-temperature exposure. These phenomena can accelerate intergranular corrosion and stress corrosion cracking of materials under industrial conditions.
The aims of the current investigation were to conduct preliminary corrosion tests on various corrosion-resistant nickel-based alloys in FLiNaK-based melts under inert atmosphere and static conditions and perform detailed analysis of the effects of microstructural changes on the corrosion resistance of nickel-based alloys as prospective structural materials for molten salt reactors.
2. Experimental
In the present study, tests for determining the corrosion properties of materials were carried out under static conditions (ampoule corrosion tests). The corrosion tests were conducted in FLiNaK-based melts. In a number of experiments, uranium tetrafluoride was added to the melt to assess the effect of the MSR main fuel component on the corrosion performance of the construction materials. The procedure for synthesis of FLiNaK was described earlier [
47,
48].
Uranium (IV) fluoride was prepared from uranyl sulfate (UO
2SO
4·3H
2O, depleted in U-235). First, uranium was reduced to an oxidation state of +4. High-purity iron powder was added to an acidified solution of uranyl sulfate to enable the reduction:
Any excess of iron was dissolved in the sulfuric acid present in the solution. Then, uranium tetrafluoride was precipitated by adding an excess solution of hydrofluoric acid:
Precipitated hydrate of uranium fluoride was washed four times with a hot 1% solution of hydrofluoric acid and then twice with distilled water. The solid was dried in air at 150 °C to remove the moisture and then dehydrated by two-stage heating under vacuum, first at 360 °C for 2 h and then at 550 °C for 1 h. The phase composition of uranium tetrafluoride was confirmed by X-ray powder diffraction analysis (PANalytical X’Pert Pro MPD, PANalytical, Almelo, The Netherlands).
Fluoride salts (the mixture of lithium, sodium, and potassium fluorides) used as the corrosive media are hygroscopic. All operations involving FLiNaK, including synthesis of the eutectic mixture, grinding, loading, and storage were carried out in a glovebox (Glovebox Systemtechnik GmbH, Malsch, Germany) in an argon atmosphere (<4 ppm O2 and <0.1 ppm H2O). The FLiNaK + UF4 salt system was prepared by mixing the salts in a FLiNaK-to-UF4 mass ratio of 93.4:6.6. Salts were mixed in the glovebox and then fused together at 850 °C in the furnace located inside the glovebox. The salts were kept at said temperature for 2 h to homogenize the melt.
The chemical composition of the electrolytes is presented in
Table 1, and the impurity content is shown in
Table 2. The results from the chemical analysis showed that addition of uranium fluoride to FLiNaK did not lead to a significant increase in the impurity content, thus confirming the purity of the synthesized UF
4.
The corrosion experiments were performed at a temperature range of 550–750 °C using a custom-built setup that included a set of steel cells closed using water-cooled lids; each cell connected to a gas-vacuum system and was heated by an external resistance furnace. The tests were performed in a high-purity argon (99.9998%) atmosphere with controlled temperature and pressure inside the retort. The setup and the methodology for conducting ampoule corrosion tests were described in detail previously [
47,
48]. This setup allows long-term corrosion tests to be performed in various working media at elevated temperatures.
Three samples of each alloy were used in the corrosion experiments. The weight of the samples was recorded prior to the test. The samples were placed in the crucibles and covered with the required amount of powdered salt. The crucibles were then covered with lids. The loading procedure was performed in an argon-filled glove box. The crucibles were transferred into stainless-steel cells, which could be tightly closed using steel lids. A metallic titanium sponge was positioned above the crucible lid in each cell to act as a getter for additional purification of the atmosphere from possible oxygen contamination. A schematic of the experimental cell used for the corrosion studies is shown in
Figure 1.
Each assembled cell was evacuated, filled with high-purity argon (99.9998%), and placed in a vertical tube furnace. A continuous argon flow of approximately 45 mL/min was maintained through the upper part of the cell throughout the experiment. The cells were heated to 650 °C, with the temperature monitored by a thermocouple positioned near the crucible (
Figure 1), and held at this temperature for 100 h. This was sufficient for assessment of the corrosion processes and estimation of their mechanisms.
After the experiment, the cells were cooled to room temperature and opened in the glovebox. The crucibles containing the samples were retrieved, and the alloy specimens were carefully separated from the molten salt. The samples were then washed sequentially with 1 M Al(NO3)3 solution and deionized water, dried, and weighed to determine mass loss. The weight change was used to calculate the corrosion rate using this gravimetric method (GM).
The concentrations of micro- and macro-components and the contents of impurities and corrosion products in the salt phase were determined using X-ray fluorescence analysis (ARL ADVANT’X 4200, ThermoFisher Scientific, Basel, Switzerland) and atomic emission spectrometry with inductively coupled plasma (Optima 2100DV, PerkinElmer, Wallingford, CT, USA). The oxygen content of the salt was determined by the method of carrier gas hot extraction (Horiba EMGA 620W/C, Horiba, Kyoto, Japan). The results from the chemical analysis allowed independent calculation of the corrosion rate values based on the mass fraction of corrosion products in the salt system (subsequently referred to as the chemical method, ChM).
For metallographic analysis, the specimens were mounted in phenol hot-mounting resin with carbon filler. Mounted samples underwent grinding in six stages using SiC papers of progressively finer grades (80 → 220 → 320 → 1200 → 2400 → 4000 grit), followed by polishing with a water-based 1 µm diamond suspension (DiADuo-2, Struers, Copenhagen, Denmark) and a final polish with colloidal silica suspension (OP-S, Struers). No etching of samples was performed.
The microstructure of the samples before and after the tests was examined by scanning electron microscopy (Zeiss Auriga CrossBeam (Carl Zeiss NTS, Oberkochen, Germany) and JSM 6490 (Tokyo, Japan) with an Oxford Inca X-Ray microanalysis setup) and optical microscopy (Olympus GX-71F, Tokyo, Japan) to assess the presence of inclusions and excess phases, as well as the nature and depth of corrosion. After the corrosion tests, the degree of intercrystalline damage, characterized by the value of the “
k-parameter”, was also determined. For this purpose, microstructure images of the sample surface of at least 0.1 cm in length (
l, cm) were analyzed, and the number of cracks (
n, pc) and their depth (
d, µm) were recorded. When cracks were not seen on the surface of the studied samples, the
k-parameter was taken to be zero. Otherwise, the arithmetic mean (
daver., µm) was calculated for all recorded cracks, and the
k-parameter (pc. × µm/cm) was calculated using the following formula (a detailed description of the applied method was given previously [
49]):
In the present study, four industrial nickel-chromium-molybdenum–based corrosion-resistant low-carbon alloys were tested, as shown in
Table 3. These alloys can be categorized into different families depending on chromium and molybdenum content. Hastelloy
® G-35
® is the alloy from the G-group and is characterized by higher chromium content. VDM
® Alloy 59 and the Russian alloy KhN62M-VI [
50] belong to the C-family. The last alloy, Hastelloy
® B-3
®, represents B-family, with increased molybdenum content and low chromium content. The G-family was designed for application in highly oxidizing aqueous systems, the C-group family offers versatility in both oxidizing and reducing media, while the B-family excels in reducing environments [
51]. The possibilities of their application at relatively high temperatures in contact with aggressive molten halides are still not clear and require deeper investigation.
The composition of the alloys in their ‘as received’ state (according to the manufacturer’s data) is listed in
Table 3. Analysis of the structure of the alloys in the initial state was also carried out (
Figure 2). The microstructure of the Hastelloy
® G-35
® (Haynes, Kokomo, IN, USA), VDM
® Alloy 59 (VDM─Metals, Werdohl, Germany), KhN62M-VI (RUSPOLYMET, Kulebaki, Russia), and Hastelloy
® B-3
® (Haynes, Kokomo, IN, USA) alloys in the ‘as received’ state represented a nickel-based fcc solid solution with a small amount of inclusions, which is typical for this class of materials [
51].
3. Results and Discussion
The employment of nickel alloys in fluoride melts, in contrast to aqueous media, inevitably introduces the problem of high temperatures, normally around 550–750 °C. In this case, the key role in the corrosion processes is played not by the increase in the kinetics of chemical reactions between the alloy components and the salt melt but by phase changes that occur in the bulk of the alloys at high rates at these temperatures. Under thermal influence, the studied alloys with initially homogeneous structure are transformed into heterogeneous systems. Such transformation can lead to the precipitation of excess phases of various nature along grain boundaries or long-range ordered structures [
46,
52,
53,
54,
55,
56,
57,
58,
59,
60,
61,
62]. The tendency to form grain boundary precipitation increases with as the temperature increases from 550 to 750 °C [
46,
52,
55,
56,
58,
59,
61,
62]. For example, no secondary chain phases were observed below 550 °C in Hastelloy
® G-35
® subjected to up to 1000 h of thermal exposure [
46]. Increasing the temperature to 650 °C can lead to the formation of various secondary phases (σ, P, α-chromium, etc.) at the grain boundaries of the studied alloys [
46,
52,
58,
60,
61], and the time required for the development of such phases in Hastelloy
® G-35
® is up to 100 h [
46]. At 750 °C, the chain precipitates are formed at a significant rate (the time of formation of precipitates in Hastelloy
® G-35
® is up to 10 h), resulting in the intensification of corrosion processes [
46].
The corrosion rates and maximum damage depth (
dmax) of the materials after 100 h corrosion tests in FLiNaK-based salt systems (with and without uranium tetrafluoride addition) at different temperatures are presented in
Table 4 and
Figure 3.
The content of corrosion products in the salt melts after the corrosion tests is summarized in
Table 5. Chromium species were the main corrosion products. Chromium, as the most electronegative element in the alloys, determined the corrosion rates and the degree of corrosion damage. The relatively high content of iron, a minor alloy component, in the corrosion products also confirmed the electrochemical nature of the corrosion processes in molten halides.
The corrosion rate measurements revealed three patterns common to all of the alloys: (a) the corrosion rate increased with increasing oxidizing capacity of the medium; (b) the corrosion rate increased with increasing chromium content in the alloys; and (c) the corrosion rate increased with increasing test temperature. In the first instance, uranium tetrafluoride increased the oxidizing ability of FLiNaK. Uranium is a polyvalent metal and capable of forming ions in different oxidation states in fluoride melts. Here, U(IV) can be reduced to U(III) in the presence of metals or alloy components. The redox potential of the U(III)/U(IV) couple in systems containing predominantly U(IV) is shifted to the region of positive values; therefore, the FLiNaK + UF
4 salt system is more aggressive than pure FLiNaK. The second pattern is associated with the phenomenon of selective etching of more negative components from the alloy. In Ni–Cr–Mo systems, chromium is oxidized first [
62,
63,
64,
65,
66,
67]. On the other hand, increasing the temperature leads both to growth of the corrosion rate and formation of secondary phases at the grain boundaries, inducing IGC processes.
To analyze the microstructural changes in the alloys, the samples were subjected to SEM analysis after the corrosion tests.
Figure 4,
Figure 5,
Figure 6,
Figure 7 and
Figure 8 show images of the materials’ microstructure after exposure in FLiNaK-based melts.
Analysis of the images shown in
Figure 4,
Figure 5,
Figure 6,
Figure 7 and
Figure 8 confirms previous conclusions that the degree of destruction of the materials increased with increasing temperature and oxidizing ability of the salt environment. After tests conducted in pure FLiNaK at 550 °C, all samples exhibited continuous uniform surface damage. In the FLiNaK + UF
4 salt system at the same temperature, the onset of localization of corrosion processes was observed for all alloys except Hastelloy
® B-3
®; the corrosion penetration depth (
dmax), however, had low values. At 750 °C, intergranular corrosion was observed on all alloys except Hastelloy
® B-3
®. The main reason for the development of IGC was the precipitation of excess phases along the grain boundaries. Thermal exposure led to the formation of secondary phases in the alloys. As a rule, this process intensifies at temperatures exceeding 600 °C, and this was confirmed by the results shown in
Figure 4,
Figure 5,
Figure 6,
Figure 7 and
Figure 8. The formation of excess phases led to heterogeneity in the alloy structure. The nature of the formation of secondary phases can be different. The secondary phases can segregate into separate phases, and can form chain arrangements or streaks. Examples of the distribution of excess phases along the grain boundaries in nickel alloys are shown in
Figure 9.
The formation of excess chain-type phases is the most dangerous case when the material is held in contact with an electrolyte, in particular with a salt melt. In this case, the excess phases are interconnected in a continuous grid. In the zone of contact of the alloy’s surface with the electrolyte, microgalvanic couples are formed, where the alloy’s grain and the excess phase act as microelectrodes. In reality, the system can be more complex, since, in addition to the excess phase and the alloy’s grain, a depletion zone is formed, and the alloy’s components diffuse from this zone to the grain boundary while the excess phases are formed. Thus, when excess phases are formed along the grain boundaries, a multielectrode system is formed, in which an anode and a cathode are present. The microanode is the phase with a lower electrode potential, and the more electropositive phase becomes the microcathode. The electrode potential of the microphase is determined by a number of factors, such as chemical composition, phase structure, presence of defects, and deformations. In addition, the formation of excess phases can provoke the occurrence of mechanical stresses along the grain boundaries, which can cause the development of IGC and intergranular stress corrosion (IGSC). Thus, the occurrence of heterogeneity along the grain boundaries of nickel alloys is a destabilizing factor that provokes more intense destruction of the material.
The chemical composition of excess phases can be used to roughly predict the role of the phase in the resulting microgalvanic system if we extrapolate the values of the corrosion rates of individual metals to the chemical composition of the excess phases. A separate series of corrosion tests was conducted with various individual metals (over 99% purity) in molten FLiNaK at 650 °C. The experiments were performed under the same conditions used for assessment of corrosion performance of the alloys. As a result, the corrosion resistance of individual metals was determined (
Figure 10). Here, the corrosion rates were determined by gravimetric and chemical analysis methods; averaged values of the corrosion rates are presented in the figure. The results confirmed our previous conclusion that chromium and iron are the main corroding elements in the studied alloys. However, in case of alloys, rather than individual metals, the activity of components in the solid solutions (alloys), the presence of defects in metallic phases, and the formation of intermetallic compounds can affect the corrosion resistance of the elements. As a result, the corrosion behavior of the alloys’ components may in some instances deviate from the corrosion resistance row shown in
Figure 10.
Under the experimental conditions, the best corrosion resistance was exhibited by electropositive metals like nickel and molybdenum; the most electronegative metals were chromium, zirconium, and iron. Thus, it can be expected that the formation of excess phases enriched in chromium will be accompanied by their intense destruction, since they will act as microanodes in the microgalvanic system (
Figure 11). An opposite phenomenon can also be expected. Enrichment of excess phases in molybdenum and nickel will contribute to the formation of microcathodes. This process does not lead to intergranular corrosion; however, in some cases IGC may develop due to selective dissolution of depleted zones from which molybdenum and nickel have diffused into the excess phases. These zones will be depleted in the most electropositive metals, and they will also have an increased concentration of defects. This will provoke the formation of a microgalvanic system in which the alloy’s grain and excess microphase will act as microcathodes, and the depleted zone will play a role of a microanode. Such behavior (formation of microcathodes) was observed in the present study for the Hastelloy
® B-3
® alloy and will be considered in more detail later.
Figure 12 and
Table 6 show the chemical composition of secondary phases (Point 2) in the Hastelloy
® G-35
® alloy and grain composition (Point 1), which corresponds to the content of main components in the bulk of the material. Excess phases in this case are significantly enriched in chromium, which points to the anodic nature of these microphases.
Figure 4 shows the nature of the destruction of Hastelloy
® G-35
® alloy samples after 100 h of contact with FLiNaK and FLiNaK + UF
4 melts. The alloy samples experienced pronounced intercrystalline damage, especially at 750 °C, which indicates the localization of corrosion processes along grain boundaries. The composition of the resulting secondary phases suggests that these phases acted as microanodes. The results of microanalysis in the destroyed grain boundary (Point 3) indicate significant chromium depletion in comparison to the bulk of the material, thus confirming the conclusion about selective dissolution of chromium-enriched secondary phases, i.e., microanodes, upon the contact with molten salt. It should also be noted that the total sum of the elements determined in the crack zone (i.e., point 3 in
Figure 12) was below 100%. This was caused by the mounting resin penetrating the crack and filling the damaged zone, and thus adding non-metallic elements to the total count of the analysis. Similar deviation from 100% was observed in all subsequent samples, where damaged zones were analyzed.
Similar observations were made for the VDM
® Alloy 59 and KhN62M-VI alloys (
Table 7 and
Table 8,
Figure 13 and
Figure 14). Excess phases (Point 2) were significantly enriched in chromium, and localization of corrosion processes along the grain boundaries was observed for all samples (
Figure 5 and
Figure 6). The composition of the secondary phases indicates that these phases acted as microanodes.
The chemical composition of the secondary phases and grains of the Hastelloy
® B-3
® alloy are shown in
Figure 15 and
Table 9. In this case, the excess phases were enriched in molybdenum and depleted in chromium and iron; moreover, the phases were distributed separately, without forming a continuous network along the grain boundaries. It is likely that the secondary phases formed during high-temperature exposure of the Hastelloy
® B-3
® alloy would act as microcathodes is the alloy were brought in contact with the electrolyte. The results showed that this alloy did not experience intercrystalline destruction; the corrosion occurred within the surface layer. However, pitting-type surface degradation suggested that, in the case of the Hastelloy
® B-3
® alloy, the corrosion process can also be localized (
Figure 7 and
Figure 8). This may result from separation of the excess phases and formation of areas depleted in electropositive elements in the alloy’s grain bulk.
Therefore, the experimental data lead to a conclusion that, in the course of formation of excess phases enriched with the most electropositive elements, such zones will act as microcathodes, and IGC will be inhibited. During enrichment of excess phases with the most electronegative components, these phases act as microanodes and, as a result, IGC develops on the contact surface with salt melts.
Thus, on the basis of the corrosion test results, an important factor affecting the corrosion resistance of materials was determined—phase instability or structural changes in materials with the fcc solid solution structure under the influence of high temperatures. Analysis of the chemical composition of the secondary phases formed in materials of various classes allowed possible mechanisms of the influence of excess phases on the corrosion resistance of nickel-based alloys in molten halides to be proposed. It was found that the most dangerous type of excess phase is phases playing the role of microanodes, since they provoke intensification of intercrystalline destruction along grain boundaries.
4. Conclusions
A series of 100 h corrosion tests of various nickel-based alloys (Hastelloy® G-35®, VDM® Alloy 59, KhN62M–VI, Hastelloy®B-3®) in FLiNaK and FLiNaK + UF4 melts was performed at 550, 650, and 750 °C. Corrosion indicators such as corrosion rates, depths of corrosion, and k-parameters were determined based on comprehensive analysis.
The key issue of nickel-based alloy corrosion in molten halides is discussed based on the obtained data. It was shown that the presence of oxidizer in the melt, namely UF4, led to a decrease in material corrosion resistance. Increasing the temperature of the tests, as well as the chromium content in Ni-Cr-Mo alloys, also accelerated corrosion processes. It was demonstrated that a decrease of corrosion resistance with chromium content in nickel-based materials was associated with selective etching of more negative components from the alloy. Increasing corrosion rates with temperature, on the one hand is explained by the Arrhenius law, and on the other hand is caused by phase changes due to thermodynamic instability of Ni-based fcc solid solution that can affect both the corrosion rate and the mechanism of material degradation.
The influence of microstructural changes in the studied alloys on the mechanism of their corrosion in molten salts is discussed in detail. It was established that the formation of anodic excess chain-type phases (enriched by electronegative components) is the most dangerous case when the material is held in contact with an electrolyte at high temperatures, and in particular with a salt melt, because these secondary phases can provoke intergranular corrosion.
It should be understood that the presented data and proposed mechanisms concern short-time ampoule corrosion tests. However, this type of express analysis combining corrosion tests and microstructure investigations enabled selection of the most promising materials from a variety of steels and alloys. During long-term thermal exposure, the microstructure of the alloys can change further. Dynamic conditions also can have an effect on corrosion processes. Therefore, long-term dynamic tests should be carried out after preliminary selection of prospective candidate materials on the basis of short-term investigations to unambiguously establish the expected service life of the material and the characteristic corrosion mechanism for each specific alloy.