Interim Report on Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953

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

doi:10.2172/4248030

Cited by 6 publications

(8 citation statements)

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“…The relative advantages and disadvantages of the remaining configurations were evaluated to determine which of the options appears to have the best chance for resulting in a successful design. This analysis: (1) identifies key requirements of the high-temperature reactor and the hydrogen production plant that affect the intermediate heat transport loop; (2) describes and justifies key assumptions used in the evaluation; (3) identifies possible configurations of the intermediate heat transport loop; (4) performs preliminary stress evaluations to determine allowable pressures and required component thicknesses based on the creep rupture strengths of currently available materials; (5) estimates the size and thermal-hydraulic performance of various components in the intermediate heat transport loop including the heat exchangers and loop piping; (6) estimates the overall cycle efficiency of each configuration; (7) determines the sensitivity of the cycle efficiency to various parameters, and (8) compares and contrasts the different options to aid in the selection of the configuration and working fluid.…”

Section: Configuration Optionsmentioning

confidence: 99%

“…Based on early R&D, the nickel-base alloy Hastelloy N was developed by ORNL for use in the MSRE. Several hundred thousand hours of corrosion experience with Hastelloy N and fluoride salts were obtained in thermal convection loop tests [3][4][5] and pumped loop tests 6 in addition to experience from the MSRE. Corrosion studies also included graphite as well as stainless steels and some refractory metal alloys, (e.g., TZM).…”

Section: A3 Past Experiencementioning

confidence: 99%

“…The presence of HF within the salt, which is used for impurity removal in the purification process, as well as moisture or oxides residing on the container or loop walls, can all lead to adverse corrosive reactions. HF can react either directly with the material forming a fluoride as noted in Equation (1) or indirectly with oxides present on the wall of the container as noted in Equations (2)(3)(4). All of these reactions should cease when the impurities have reacted.…”

Section: A4 Understanding Derived From Past Experiencementioning

confidence: 99%

“…As alluded to earlier, oxidation of one of the constituents of the material by the reduction of a less stable impurity metal fluoride initially in the salt such as iron or nickel fluoride can occur. 2,3 Examples of this include:…”

Section: A4 Understanding Derived From Past Experiencementioning

confidence: 99%

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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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Section: Configuration Optionsmentioning

confidence: 99%

Section: A3 Past Experiencementioning

confidence: 99%

Section: A4 Understanding Derived From Past Experiencementioning

confidence: 99%

Section: A4 Understanding Derived From Past Experiencementioning

confidence: 99%

See 2 more Smart Citations

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

View full text Add to dashboard Cite

show abstract

“…Design of a chemically stable system utilizing molten fluoride salts, therefore, demands the selection of salt constituents that are not appreciably reduced by available structural metals and the development of containers whose components are in near thermodynamic equilibrium with the salt medium. As a result of these studies, the development of a preliminary reactor experiment was undertaken using a nickel-base alloy containing 15 Cr, 7 Fe,* and a fuel salt of the system NaF-ZrF 4 -UF 4 • This reactor experiment, although of intentionally short duration, successfully demonstrated the feasibility of the fluoride fuel concept [6,7].…”

Section: Introductionmentioning

confidence: 99%