High Temperature Corrosion of Structural Alloys in Molten Li<sub>2</sub>BeF<sub>4</sub>(FLiBe) Salt

Zheng, Guiqiu; Carpenter, David; Hu, Lin‐Wen; Sridharan, Kumar

doi:10.1002/9781119323624.ch9

Cited by 3 publications

(5 citation statements)

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“…9 In the reactor environment, the strong radiation fields can exacerbate alloy corrosion in molten salt, but the mechanisms are not conclusively understood. 10 Hastelloy N Ò and 316 stainless steel are being actively considered as structural materials for the FHR, and corrosion experiments of these alloys in either static or dynamic systems have been conducted in laboratories to support the development of the FHR. [11][12][13][14][15] This work provides a brief overview of the corrosion results of these two alloys in molten FLiBe salt, and the role of graphite on corrosion.…”

Section: Introductionmentioning

confidence: 99%

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Zheng

Sridharan

2018

JOM

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Hastelloy N Ò , a nickel-based alloy, and 316 stainless steel are among the candidate structural materials being considered for the construction of the molten salt reactor (MSR). Most of the proposed MSR concepts use molten fluoride salts as coolant which can be quite corrosive to structural alloys. The results of studies on the corrosion behavior of the two alloys in molten Li 2 BeF 4 (FLiBe) salt at 700°C are discussed. This salt is being considered as the primary coolant for MSR designs featuring solid fuel particles, but the reported results also provide insights into the corrosion in MSR designs where the uranium fuel is dissolved in the molten fluoride salt. Corrosion was observed to occur predominantly by de-alloying of Cr from the alloy surface and into the molten salt, with more pronounced attack occurring along the grain boundaries than in the bulk grains. The magnitude and the mechanisms of corrosion were different for corrosion tests performed in graphite and metallic capsules, a result warranting recognition given the coexistence of structural alloys and graphite in the molten salt medium in the MSR.

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Section: Introductionmentioning

confidence: 99%

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Zheng

Sridharan

2018

JOM

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“…Samples in graphite crucibles lost more weight than those in metal-lined crucibles. For in-reactor corrosion, neutron radiation increased weight loss relative to out-of-reactor tests by factors of 10, 5, and 2 for 316L in a graphite crucible, 316L in a 316 stainless steel-lined crucible, and Hastelloy N in a Ni-lined crucible, respectively (138). Hastelloy N in the graphite crucible gained weight, which Zheng et al (138) attribute to the possible formation of carbides.…”

Section: Windows Of Susceptibilitymentioning

confidence: 97%

“…For in-reactor corrosion, neutron radiation increased weight loss relative to out-of-reactor tests by factors of 10, 5, and 2 for 316L in a graphite crucible, 316L in a 316 stainless steel-lined crucible, and Hastelloy N in a Ni-lined crucible, respectively (138). Hastelloy N in the graphite crucible gained weight, which Zheng et al (138) attribute to the possible formation of carbides. The mechanisms for the accelerated corrosion with neutron irradiation and in the presence of C are not clear.…”

Section: Windows Of Susceptibilitymentioning

confidence: 97%

“…The effects of C in the system can also lead to difficulties in the interpretation of irradiation-corrosion studies because graphite crucibles are commonly used in experiments with molten salts. For example, Zheng et al (138) studied Hastelloy N and AISI 316L in Li-7enriched FLiBe, using both metal-lined and graphite crucibles. Samples in graphite crucibles lost more weight than those in metal-lined crucibles.…”

Section: Windows Of Susceptibilitymentioning

confidence: 99%

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Effects of Radiation-Induced Defects on Corrosion

Schmidt

Hosemann

Scarlat

et al. 2021

Annu. Rev. Mater. Res.

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The next generation of nuclear reactors will expose materials to conditions that, in some cases, are even more extreme than those in current fission reactors, inevitably leading to new materials science challenges. Radiation-induced damage and corrosion are two key phenomena that must be understood both independently and synergistically, but their interactions are often convoluted. In the light water reactor community, a tremendous amount of work has been done to illuminate irradiation-corrosion effects, and similar efforts are under way for heavy liquid metal and molten salt environments. While certain effects, such as radiolysis and irradiation-assisted stress corrosion cracking, are reasonably well established, the basic science of how irradiation-induced defects in the base material and the corrosion layer influence the corrosion process still presents many unanswered questions. In this review, we summarize the work that has been done to understand these coupled extremes, highlight the complex nature of this problem, and identify key knowledge gaps. Expected final online publication date for the Annual Review of Materials Science, Volume 51 is August 2021. Please see http://www.annualreviews.org/page/journal/pubdates for revised estimates.

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“…The profound effect of trace impurities in molten salt on its corrosivity and contamination from corrosion products further makes experimental work extremely challenging particularly at higher temperatures . Hence, the implications on the corrosion effect of FLiBe such as the formation of oxides by the reaction with water and with reactor container metallic alloys must be addressed. ,, To limit the extent of the corrosion, molten salt redox potential control has been proposed with either the addition of a metallic buffer, a soluble redox couple buffer, or overhead gas control. In addition to the redox potential, fluoroacidity, which describes the coordination of the solvent, is also an important parameter of the salt.…”

Section: Introductionmentioning

confidence: 99%

Temperature-Dependent Properties of Molten Li₂BeF₄ Salt Using Ab Initio Molecular Dynamics

et al. 2021

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Molten lithium tetrafluoroberyllate (Li 2 BeF 4 ) salt, also known as FLiBe, with a 2:1 mixture of LiF and BeF 2 is being proposed as a coolant and solvent in advanced nuclear reactor designs, such as the molten salt reactor or the fluoride salt cooled high-temperature reactor. We present the results on the structure and properties of FLiBe over a wide range of temperatures, 0−2000 K, from high-throughput ab initio molecular dynamics simulation using a supercell model of 504 atoms. The variations in the local structures of solid and liquid FLiBe with temperature are discussed in terms of a pair distribution function, coordination number, and bond angle distribution. The temperature-dependent electronic structure and optical and mechanical properties of FLiBe are calculated. The optical and mechanical property results are reported for the first time. The results above and below the melting temperature (∼732 K) are compared with the experimental data and with data for crystalline FLiBe. The electronic structure and interatomic bonding results are discussed in correlation with the mechanical strength. A novel concept of total bond order density (TBOD), an important quantum mechanical parameter, is used to characterize the internal cohesion and strength in the simulated models. The results show a variation in the rate of change in properties in solid and liquid phases with anomalous behavior across the melting region. The observed trend is the decrease in mechanical strength, band gap, and TBOD in a nonlinear fashion as a function of temperature. The refractive index shows a surprising minimum at 850 K, among the tested temperatures, which lies above the melting point. These findings provide a new platform to understand the interplay between the temperature-dependent structures and properties of FLiBe salt.

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High Temperature Corrosion of Structural Alloys in Molten Li₂BeF₄(FLiBe) Salt

Cited by 3 publications

References 16 publications

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Effects of Radiation-Induced Defects on Corrosion

Temperature-Dependent Properties of Molten Li₂BeF₄ Salt Using Ab Initio Molecular Dynamics

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High Temperature Corrosion of Structural Alloys in Molten Li2BeF4(FLiBe) Salt

Cited by 3 publications

References 16 publications

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors

Effects of Radiation-Induced Defects on Corrosion

Temperature-Dependent Properties of Molten Li2BeF4 Salt Using Ab Initio Molecular Dynamics

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Product

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High Temperature Corrosion of Structural Alloys in Molten Li₂BeF₄(FLiBe) Salt

Temperature-Dependent Properties of Molten Li₂BeF₄ Salt Using Ab Initio Molecular Dynamics