Interim Report on Corrosion by Zirconium-Base Fluorides

Adamson, G.M.; Crouse, R.S.; Manly, W. D.

doi:10.2172/4107813

Cited by 7 publications

(9 citation statements)

References 0 publications

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“…LiF-KF 492ºC LiF-RbF (44)(45)(46)(47)(48)(49)(50)(51)(52)(53)(54)(55)(56) 470ºC LiF-NaF-KF ("FLiNaK") (46.5-11.5-42) 454ºC…”

Section: Alkali Fluorides Zrf 4 Salts Bef 2 Saltsmentioning

confidence: 99%

“…A good understanding of fuel-salt corrosion was developed, but we do not know the precise mechanism of persistent (i.e., mass-transfer) corrosion of nickel alloys with coolant salts. We must assume that redox-sensitive species, such as Cr(II/III) and Fe(II/III), are important factors in this process [51,67]. However, with limited analytical resources, other factors apparently present in previous studies must be evaluated to identify all truly significant trends.…”

Section: Coolant Salt Selection Factors Related To Corrosionmentioning

confidence: 99%

“…Inconel was more severely corroded with fuel salts made with all alkali-metal fluorides than those made with NaF-ZrF 4 mixtures, suggesting that the chemical composition of the fuel salt played a significant role in controlling the corrosion chemistry. Extensive development in materials research [49][50][51][52][53] resulted in the production of an improved nickel-base alloy, INOR-8 (17% Mo, 7% Cr, 5% Fe, balance Ni).…”

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confidence: 99%

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Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR)

Williams¹

2006

254

255

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“…LiF-KF 492ºC LiF-RbF (44)(45)(46)(47)(48)(49)(50)(51)(52)(53)(54)(55)(56) 470ºC LiF-NaF-KF ("FLiNaK") (46.5-11.5-42) 454ºC…”

Section: Alkali Fluorides Zrf 4 Salts Bef 2 Saltsmentioning

confidence: 99%

Section: Coolant Salt Selection Factors Related To Corrosionmentioning

confidence: 99%

mentioning

confidence: 99%

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Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR)

Williams¹

2006

254

255

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“…However, the overall efficiency of the electrical production process will be reduced. In the parallel heat exchanger option, which is illustrated in Figures 2,4,6,and 7, the hottest fluid is divided, with most going towards the PCU and the remainder going towards the hydrogen production plant. This configuration is more complicated, but results in a higher overall efficiency because both the electrical and hydrogen production plants see the maximum possible temperature.…”

Section: Design Configurationsmentioning

confidence: 99%

“…With these options, a small compressor or blower is required to compensate for the pressure loss across the IHX or SHX and allow the fluid streams to mix downstream of the recuperator. The final option uses a SHX as shown in Figures 3,4,5,and 6. This option utilizes a third or tertiary coolant loop that provides additional separation between the nuclear and hydrogen plants, which should increase the safety of both plants and may make the nuclear plant easier to license.…”

Section: Design Configurationsmentioning

confidence: 99%

Thermal-Hydraulic Analyses of Heat Transfer Fluid Requirements and Characteristics for Coupling A Hydrogen Production Plant to a High-Temperature Nuclear Reactor

Davis¹,

Oh²,

Barner³

et al. 2005

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The Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the hightemperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant, may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single-and dual-purpose facilities need to be understood. Seven possible configurations for a system that transfers heat between the nuclear reactor and the hydrogen and/or electrical generation plants were identified. These configurations included both direct and indirect cycles for the production of electricity. Both helium and liquid salts were considered as the working fluid in the intermediate heat transport loop. Methods were developed to perform thermalhydraulic and cycle-efficiency evaluations of the different configurations and coolants. The thermalhydraulic evaluations estimated the sizes of various components in the intermediate heat transport loop for the different configurations. The relative sizes of components provide a relative indication of the capital cost associated with the various configurations. Estimates of the overall cycle efficiency of the various configurations were also determined. The evaluations determined which configurations and coolants are the most promising from thermal-hydraulic and efficiency points of view. These evaluations also determined which configurations and options do not appear to be feasible at the current time.

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